ML20127A741
| ML20127A741 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Browns Ferry |
| Issue date: | 07/07/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127A737 | List:
|
| References | |
| FOIA-84-794 NUDOCS 8307180387 | |
| Download: ML20127A741 (47) | |
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7[7[23 7590-01 UNITED STATES WUCLEAR REGULATORY COMMISSION TENNESSEE VALLEY AUTHORITY DOCKET NOS. 50-259, 50-260, 50-296 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPGSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AND OPPURTUNITY FOR HEARING
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The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to Facility Operating Licenses No. DPR-33, DPR-52 and DPR-68, issued to Tennessee Valley Authority (the licensee), ~ for operation of
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the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3 located in Limestone
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County, Alabama.
The amendments would revise the Technical Specification = of the operating licenses to change the required surveillance interval' for testing the Standby Gas Treatment, System from once per year to once per operating cycle to be consistent with the requirements in the BWR Standard Technical Specifications (NUREG-0123).
The proposed change would also require concurrent. demonstration of the operability of the Standby Gas Treatment System with the Primary Containment Isolation logic circuitry rather than testing of the Standby Gas Treatment System al one'.
The change would resolve ambiguities in the present wording of the specifications regarding the scope and frequency of the testing.
These revisions to the Technical Specifications would be made in response to the licensee's application dated June 13, 1983.
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7590-01 Before issuanc'e of the proposed li' cense amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended-(the Act) and the Commission's regulations.
The-Commission has made a proposed determination that the amendment request involves no significant hazards consideration.
Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the propossd amendment would not (1) involve a significant increase in. the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any.
accident previously evaluated; or (3) involve a'significant reduction in a margin of safety.
The Commission has provided guidance for the application of these criteria 'by providing examples of amendments that are ccasidered not likely. to involve significant hazards considerations (48 FR 14870).
These examples i
include:
"(i) A purely administrative change to the technical specifications:
for example, a change to achieve consistency throughout the technical specifications, correction of an error, or a change intomenclature"; and
"(vi) A change which either may result in.some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all
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acceptable criteria, with respect to the system or component specified in the Standard Review Plan..."
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3 The first change proposed by the licensee to decrease the surveillance
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frequency from once' per year to once per operating cycle could be considered a change which either may result in some increase to the probability or consequences of a previously-analyzed accident or may reduce in some way a safety margin.
However, the staff has concluded-that the results of the pro -
posed change are clearly within all acceptable. criteria with respect to the system or component specified in the Standard Review Plan. The Standard Review Plan (NUREG-0800) is' used by the staff in perfoming safety reviews 9
of applications to construct or operate nuclear power plants.
The Standard Review
. Plan presents acceptable design and perfonnance characteristics for systems and components. The Standard Technical' Specifications are recognized by the staff as an acceptable means of implementing NRC requirements as specifi;ed' in the Standard Review Plan regarding operability and surveillance testing of these systems and comporants.
The change in the Technical Specifications proposed by the licensee is in accordance with the BWR Standard Technical Specifications and thus is within the acceptance criteria specified in the Standard Review Plan.
Thus, the first change regarding surveillance frequency falls.within example (vi) of changes that are not likelf to involve significant hazards consideraitons and on this basis the staff proposes to find that this change does not involve significant hazards considerations.
The second change to the Technical Specifications requested by the licensee would replace the wording in the requirement for surveillance testing the Standby Gas Treatment System with the language in Section 4.6.5.1 of the BWR Standard Technical Specifications. The change would resolve ambiguities in the present wording as to whether a logic functional test is required, how
. 4 7590-01
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much of. the total system is to be teste'd and th; frequency of the testing.
.The proposed change is considered to be an administrative change since the-change only clarifies existing requirements and does not alter either their intent or frequency.
Thus, this change falls within examle (i),of changes that' are not likely A
to involve significant hazards considerations and on this basis the staff pro-pqses to find that this change does not involve significant hazards considera-tions.-
1The Commission is seeking public conments on this proposed determination.
Any comments received within~ 30 days after the date of publication of this notice will be considered.in making any final determination.
The Commission will-not normally make a final determination unless it receives a request for a heasing.
Comm nts should be addressed to the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, D.C.
20555, Attn:
Docketing - and '
Service Branch.
By August 7,1983, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for leave'to ' intervene.
Request for a hearing and petitions for 4
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7590-01 leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an At'omic Safs.ty and Licensing Board, designated by the Commission or by the Chairman of the At'mic Safety and Licensing o
Board Panel, will rule on the request and/or petition and the Secretary o'r the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 52.714, a petition for ' leave to intervene-shall set forth w.ith particularity the interest of the petitioner in the proceeding,
- and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:
(1) the nature of the petitioner's right under the Act to be made a party' to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the~ proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the proceeding.as 'to which petitioner wishes to intervene.
Any person who has I
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7590-0
- filed a petition for leave to intervene or who has been ' admitted as a party may amend the petition without requesting leave of the Board up to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than fifteen (15.) days prior to the first prehearing conference sdheduled in the proceeding, a petitioner shall file a supplement to the petition '
to intervene which must include a list of the contentions which are sought to be litigated in the matter,- and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration.
A petitioner who fails to -
file such, a supplement which satisfies these requirements with respect to at least one contention will not be pemitted to participate as a party.
Those pemitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the
. opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses.
If a hearing is requested, the Commission will make a final detemination on the issue of no.significant hazards consideration.
The final determina-tion will serve to decide when the hearing is held.
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7 590-: ',
'If the final determination is tha~t the amendment r.equest involves no significant hazards consideration, the Commission may issue the amendment and make it effective, notwithstanding the request for a hearing.
Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment involves a significant hazards consideration, any hearing held would take place before the is'suance of any amendment.
Nomally, the Commission will not issue the amendment until the expir-ation of the 30-day notice period. However, should circumstances change during the notice period such that failure to act in a timely way would result, for exanple, in derating or shutdown of the facility, the Commissiqn may issue the license amendment before the expiration of the 30-day notice -
period, provided that its final determinatio~n is that the amendment involves no significant hazards consideration. The final detemination will consider all public and Stata comments received.
Should the Commission take this action, it will publish a notice of issuance and provide for opportunity for a hearing after issuance.
TheCommissionexpectsThattheneedto take this action will occur very infrequently.
A _ request for a hearing or a petition for. leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission,-
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7590-01 ashington, D.C. 20555, Attention: Docketing and Service Branch, or n.3y be Oliv0 red to the Commission's Public Document Room,1717 H. Street, N.W.,
ashington, D.C., by the above date.
Where petitions are filed during the a'st. ten (10) days of the notice period, it,is requested that the petitioner rom:tiy so infom the Commission by a toll-free telephone call to Western
- nion at (800) 325-6000' (in Missouri (800) 342-6700). The Western Union
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,p:rator should be given Datagram Identification Number 3737 and the following tessage addressed to Domenic B. Vassallo:
petitioner's name and telephone number; lato.p:tition was mailed; plant name; and publication date and page number
)f this FEDERAL REGISTER notice.
A copy of the petition should also be sent
- o the Executive Legal Director, U.S. Nuclear Regulatory Commission, Washington,
-).0.
20555, and to H. S. Sanger, Jr., Esquire, General Counsel, Tennessee Valley Authority,100 Commerce Avenue, EllB 33C, Knoxville, TN 37902.
Ncntimely filings of-petitions for leave to intervene, amended petitions, supple ental petitions and/or requests for hearing will not be entertained absent a determination by' the Commission, the presiding officer or the Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of' a late petition and/or request. That detemination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714 ( d).
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.d 7590-01
- For further details with respect to this action, see the application for amendment which is available for public inspection at the. Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Athens Public Library, South and Forrest, Athens, Alabama 35611.
Dated at Bethesda, Maryland, this 7th day 'of July 1983.
FOR THE NUCLEAR REGULATORY COMMISSION 9
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing e
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33S74 Federal Register / Vol. 48. No.142 / Friday. July 22. 1983 / Notices Place: The Na tional Science Foundation.
Hearing.** The amer $dment requested significant increase in the probability or Room 602.1800 G Street. N.W. Washington, would revise the Technical consequences of an accident previously D C 20550.
Specifications to recognize steam evaluated; or (2) create the possibility of Type of Meetins Closed-Contact Person: Dr. lames Fred Hays, generator tube repair techniques, other a new or different kind of accident from than plugging, provided such techniques any' accident previously evaluated; or (3) at ons ience F u da o ash a o are approved by the Commission.
involve a significant reduction in a D.C. 2C 550, telephone: (202) 357-7958.
The Board is comprised of tne margin of safety.
Purpose of Committee:To provide advice, following administrative judges:
The Commission has provided end recommendations conceming support for SheldonJ.Wolfe. Chairman Atomic guidance for the application of these research in Earth Sciences.
Agenda: To review and evaluate research Safety and Ucensing Board Panel, criteria by providing examples of proposals and projects as part of the U.S. Nuclear Reguistory Commission.
amendments that are considered not Washington. D.C. 20555 likely to involve a significant hazards e sonfo los e proposals being Dr. David L Hetrick. Professor of consideration (48 FR 14870). One such reviewed include information of proprietary Nuclear Engineering. University of example is a change that constitutes an i'
or t.onfidential na ture. including technical Arizona.Tuscon. Arizona 85721 a dditional limita tion, res triction. or information: financial data, such as salaries; Dr. James C. Lamb.111. Department of control not presently included in the end personalinformation conceming Environmental Sciences and individuals associated with the proposals.
Technical Specifications, for example. a These matters are within exemptions (4) and Engineering. University of North more stringent surveillance requiuent.
6)of U.S C. 552b[c). Gcvernment in the Carolina. Chapel Hill. North Carolina The proposed amendment, which 27514 increases the required capacity of the Authc,nty-This determination was made by Issued at Bethesda, Maryland. this 15th day inverters from 30 KVA to 45 KVA.
the Committee Officer Management Officer of July.1983.
Constitutes an additionallimitation than pursuant to provisions of Section 10(d) of B. Paul Coner, Jr that is currently required by the Pub. f.92-453. the Co nmittee Management Officer was delegated the authority to make ChiefAdministmtive/udge. AtomicSofety Technical Specifica tions. Therefore.
such dete mations by the Director. NSF.
and2icensing BoardPtrnel.
based on this consideration and the n um rw rm nuniq criteria mentioned above, we have made M. Rebecca Winklee.'
sah 76aket-a, a proposed determination that this Committee bfanagement Coordinator.
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amendment request involves no July 19.1983.
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significant hazards consideration.
y (Docket No. 50-275) in Doc u.isne rw r-n-as. us sel The Commission is seeking public ou.s a coes rssm as Pacific Gas and Electric Co.;
comments on this proposed Consideration of issuance of determination. Any comments received Amendment to Facility Operating within 30 days after the date of NUCLEAR REGUULTORY Ucense and Proposed No Significant publication of thir notice ill be COfAMISSION Hazards Consideration Determination considered in making any f:nal loocket No. 50-289-OLA; ASt.BP No. 83-and Opportunity for Hearing determination. The Commission will not ncrmally make a final determination 49t-o4oLAI
%e U.S. Nuclear Regulatory unless it receives a request for a M ;tropolitan Edison Co., et al.-
Commission (the Commission)is hearing.
Establishment of Atomic Safety and consideringissuance of an amendment Comments should be addressed to the Ucensing Board to Facility Operating Ucense No. DPR-Secretary of the Commission. U.S.
- 76. Issued to Pacific Gas and Electric Nuclear Regulatory Commission.
Pursuant to delegation by the Company (the licensee), for opera tion of Washington. D.C. 20555. Attn.:
Commission dated December 29,1972, the Diablo Canyon Unit 1. nuclear Docketing and F rvice Branch.
published in the Federal Register (37 FR power plant located in San Luis Obispo By August 22,1983. the licensee may 25710) (1972), and il 2.105. 2.700. 2.702 County, California.
file a request for a hearing with respect 2.714,2.714a. 2.717. 2.721 and 2.772(j) of The amendment would update to issuance of the amendment to the the Commission's Regulations, as sections 3.8.2.1 and 3.8.2.2 of the facility amended, and the Commission's Order Technical Specifications to reflect the subject facility operating license and d:ted July 15,1983. an Atomin Safety installation of two new 7.5 KVA any persons whose interest may be end Ucensing Board is being established inverters to increase the capacity of the. affected by this proceeding and who wishes to participate as a party in the in the following proceeding to rule on Class IE instrument AC system from 3 '
proceeding must file a written petitiori i
pttitions for leave to intervene and/or KVA to 45 KVA in accordance with the for leave to intervene. Request for a g
riquests for hearing and to preside over licensee's application dated December hearing and petitions for leave to the proceeding in the event that a 19.1982.
hering is ordered.
Before issuance of the proposed withe Commission's " Rules of Practlce intervene shall be filed in accordance M:tropolitan Edison Co et al Three license amendment. the Commission for Domestic Ucensing Proceedings' in
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u a ation Um' will have made findings required by the 10 CFR Part 2. If a request for a hearing i;g
,g DPR Atomic Energy Act of 1954., as amended or petition for leave to intervene,is filed (the Act) and the Commission,a by the above date, the Commission or This Board is being constituted regulations.
an Atomic Safety and Ucensing Board, pursuant to a notice pi.blished by the The Comrnission has made a proposed C:mmission on May 31.1983 in the determination that the amendment designated by the Commission or by the Chairman of the Atomic Safety and fed:rel Register (48 FR 24231-32) request involves no significant hazards Ucensing Board Panel, will rule on the iemInded June 14.1983 (48 FR 27328)).
consideration. Under the Comuission's request and/or petition and the
" Issuance of Amendment to Facility regulations.10 CFR 50.92. this means Secretary of the designated Atomic Operating Ucenses and Proposed no Significant Hazards Consideration that operation of the facility in Safety and ucensing Board will1: sue a accordance with the proposed notice of hearing or an appropriate D; termination and Opportunity for amendment would not:(1) Involve a order.
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Federal Register / Vol. 48. No.142 / Friday. July 22. 1983 / Notices 33575 As required by to CFR 2.714. a If the final determination is that the request, that the petitioner has made a petition for leave to intervene shall set amendment involvu a significant substantial showing of good cause for forth with particularly the interest of the hazards consideration, any hearing held the granting of a late petition and/or petitioner in the proceeding, and how would take place before the istuence of request.That determination will be that interest may be affected by the any amendment.
based upon a balancing of the factors results of the proceeding ne petition Normally, the Commission will not specified in 10 CFR 2.714(a)(1)(i)-(v) and should specifically explain the reasons issue the amendment until the 2.714(d).
why intervention should be permitted expiration of the 30-day notice period.
For further details with respect to this with particular reference to the However, should circumstances change action, see the application for
" following factors:(1)The nature of the during the notice period such that failure amendment dated December 19,1982, petitioner's right under the Act to be to a'et in a timely way would result, for which is available for public inspection made a party to the proceeding:(2) the example,in derating or shutdown of the at the Commission's Public. Document nature and extent of the petitioner's facility, the Commission may issue the Room.1717 H Street. NW., Washington.
property, financial, or other interest in license amendment before the
.D.C., and at the California Polytechnic the proceeding: and (3) the possible expiration of the 30-day notice period.
State University 1.ibrary. Documents effect of any order which may be provided that its. final determination is and Maps Department. San Luis Obispo, entered in the proceeding on the that the amendment involves no Californla 93407.
petitioner's intere:t. ne petition should significant hazards consideration. The also identify the specific aspect (s) of the final determination will consider all Dated at Bethesda, Maryland, this 15th day oljuly 1983.
subject matter of the proceeding as to public and State comments received.
which petitioner wishes to intervene.
Should the Commission take this action.
For the Nuclear Regulsory Commission,
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,,3 y,,,, gj,j,j,,,f Any person who has filed a petition for it will publish a notice ofissuance and leave to intervene or who has been provide for opportunity for a hearing admitted as a party may amend the after issuance. The Commission expects g.,,"####
petition without requesting leave of the that the need to take this action will tMDma m M m aosm)
Board up to fifteen (15) days prior to the occur very infrequently.
first prehearing conference scheduled in A request for a hearing or a petition the proceeding, but such an amended for leave to intervene must be filed with MN 50-M ~
petition must satisfy the specificity the Secretary of the Commission. U.S.
requirements described above.
Nuclear Regulatory Commission.
Wisconsin Electric Power Co.; Point Not later than fifteen (15) days prior to Washington, D.C. 20555. Attention:
Beach Nuclear Power Plant. Unit No.1; the first prehearing conference Docketing and Service Section. or may Availability of Draft Environmental scheduled in the proceeding, a petitioner be delivered to the Commission's Pubic Statement shall file a supplement to the petition to Document Room.1717 H Street. NW intervene in the proceeding which must.
Washington. D.C. by the above date.
Notice is hereby given that a Draft include a list of the contentions which Where petitions are filed during the last Environmental Statement (DES) are sought to be litigated 5 the matter, ten (10) days of the notice period. It is (NUREG-1011) has been prepared by the and the bases for each contention set regt.ested that the petitioner promptly so Commission's Office of Nuclear Reactor forth with reasonable specificity.
Inform the Commission by a toll-free Regulation related to the repair of steam Contentions shall be limited to matters telephone call to Western Union at (800) generators at the Point Beach Nuclear within the scope of the amendment.
325-6000 (in Missouri (8C0) 342-6700).
Power Plant. Unit No, I which'is located under cons.deration. A petitioner who "Ihe Westem Union operator:hould be in the Town of Two Creeks. Manitowoc falls to file such a supplement which given Datagram Ideytification Number County Wisconsin.
satisfies these requirements with respect 3737 and the following message This Draft Environmental Statement to at least one contention will not be addressed to George W. Knighton:
addresses the environmentalimpacts of permitted to participate as a party.
petitioner's name and telephone the proposed steam generator repairs Those permitted to intervene become number; date petition was mailed: plant and alternatives thereto.
parties to the proceeding subject to any name; and publication date and page This DES is available for inspection limitations to the order granting leave to number of this Federal Register notice.
by the public in the Commission's Public intervene, and have the opportunity to A copy of the petition should also be Document Room a t 1717 H Street. NW.,
participate fully in the conduct of the sent to the Executive Legal Director.
Washington, D.C. 20555 and in the hearing. Including the op~portunity to U.S. Nuclear Regulatory Commission.
Documents Department I.ibraryc present evidence and cross-examine Washington D.C. 20555, and to Philip A.
University of Wisconsin-Stevens Point.
witnesses.
Crane, Jr.. Esq., Pacific Cas and Electric Stevens Point. Wisconsin and the Joseph if a hearing is requested the Company 77 Beale Street. San P. Mann Public Library.1518 Sixteenth Commission wi make a final Francisco, California 94106 and Norton. Street. Two Rivers. Wisconsin.The determination on the issue of no Burke. Berry and French P.C Attn: Draft Environmental Statement is also ' significant hazards consideration.The Bruce Norton. Esq.,2002 East Osborn being made available at the Bay Lake final determination will serve to decide Road. Phoenix, Arizona 85016. attorneys Regional Planning Commission, when the hearing is held. for the licensee. University of Wisconsin-Green Bay, if the final determination is that the Nontimely filings of petitions for leave Socio-Ecology Building. Suite 450. Green amendment request involves no to intervene, amended petitions. Bay, Wiscon In 54302. Requests for significant hazards consideration, the supplemental petitions and/or requests copies of the DES (NUREC.-10111 should Commission may issue the amendment for hearing will not be entertained be addressed to the U.S. Nuclear and make it effective, notwithstanding absent a determination by the Regulatory Commission. Washington, the request for a hearing. Any hearing Commission, the presiding officer or the D.C. 20555. Attention: Director, held would take place after issuance of Atomic Safety and Licensing Board TechnicalInformation and Document the amendment. designated to rule on the petition and/or Control.
( = b
- );534 Tederal Register / Vol. 48. No.101 / Thursday. Augint 18.1rin3 / Notices
- gnif.n.mt hoz..r.fm t.unsideration. The Phm ais. Arizonu 85010 attr rney a for Atomic F.nergy Act uf 19"A. us amenderd final determination will serve to decide the licensee.
(the Act) and the Cummission's when 'he hearing is held. Nnntimely filings of petitions for leave regulations. If the final determination is that the to intervene, amended petitions. The Cummission has made a proposed amendrnent request involves no supplemental petitions and/or requests dutcrmination that the amendment r.igrdfh. ant hazards consideration, the for hearing will not be entertained request im olves no significant hazards Con.n:ission mny issue the amendment absent a determination by the consideration. Under the Commission's i end rnake it effective. notwithstanding Commission, the presiding officer or the regulations in 10 CFR 50.92 this means d.e rem st for a hc aring. Any hearing Atorr.ic Safety and Licensing Board that operation of the facility in Hd va.clJ take p!ar e after issuance of designeted to rule on the pa tition and/or ccco-dance with the proposed me a.odment. request, that the petitioner has made a araendment would not (1) involve a If t'.c final dehrn@ction is that the substential showing of yood cause for signif r int increase in the probability or ,.mndment intohes a si y.ificant the grs.nting of a late petitioner and/or consequein.es of an accident previously t haz:.rds consider:.! ion. any hearing held re ;uest. The determination will be i satuated or (2) create the pessibility or would teke place before 6e istuance of bued upon c be!ancing cf the factors a new differr.nt kind of accident from riy amendment-6pecified in 10 CFR 2.714(a)(1)(i)-(v) and any accident pr eviously es aluated. or (3) Normally, the Commission will not 2.174(d). mvols e a signific. int rtduction in a i> sue the amendment until the For further details with respect to this margin of safety. expiration of the 30-day notice period. action, see the application for The Commission's proposed , flowever, should circumstances change amendment dated June 23.1983, and determination is based on its finding during the notice period such that failure supplementalinformation dated July 28. that the revised Ph) sical Security Plan to act in a timely way would result, for 1983 which are available for public would continue to meet the general and examt.fc. m derating or shutdown of the inspection at the Commission's Public specific requirements of the regulations fr.cility, the Commission rnay issue the Document Room.1717 H Street. NW, on physical security contained in 10 CFR license amendment before the Washington. D.C. and at the California 73.55 [b) through (h) and could improve expiration nf the 30. day notic,e period. Polytechnic State University Library. access to vital equipment where a short provided that its final determmation is Documents and Maps Department. San response time is essential.This thnt the amendment involves no Luis Obispo. California 9340'/. amendment will delete the use of certain knal e e Dated at Bethesda, Maryland, this 12th day internal controls that are not mandated inat il onsi ra public and State comments received, of August 383. h ngulatory mqdrements for acun to Should the Commission take this action. For the Nuclear Regulatory Commission. certain vital areas. Moreover, no other . It will publish a notice ofissuance and George W. Knighton, nuclear power plant in the United States of America contains the above cited provide for opportunity for a hearing Chief. Licensing Becoch No. s. Division of requirement that the licensee proposes after issuance. The Commission expects Licensins-to delete.The bases for the staffs thit the need to take this action will tra on. r.i.ntr.ex s u =l determmation that the proposed occur very infrequently. es tsoo st-as amendment involves no significant A request for a hearing or a petition f;r leave to intervene must be filed with / hazards consideration has been 4 th:a Secretary of the Commission. U.S. F (Docket No. 50-275) documented: however,it la being. Nuclear Regulatory Commission. Pacific Gas & Electric Co.; p us t to 73 1' Washington. D.C. 20555. Attention: Consideration of issuance of The Commission is seeking public de v ed to h asio ic U ense o No Sig f cant [e[e*rminat on. co ments received n Washington. D C. by the ab 'dat Hazards, Consideration, within 30 days after the date of Determination, and Opportunity for publication of this notice will be Where petitions were filed du ng t e Hearing last ten (10) days of the notice period. it considered in making any final is requested that the petitioner prnmptly The U.S. Nuclear Regulatory determination. The Commissicn will not so inform the Commission by a toll free Commission (the Commission)is . normally make a finsi determination telephone call to Western Union at (800) considering issuance of an amendment unless it receives a request for a 325-6000 (in Mis souri (800) 342-6700). to Facility Operating License No. DPR-hearing. The Western Union operator should be 76, issued to Facific Gas & Electric Comments should be addressed to the i given Datagram identification Number Company (the Ucensee). for operation of Secretary of the Commission. U.S. 3737 and the following message the Diablo Canyon. Unit 1 Nuclear Nuclear Regulatory Commission, cddressed to Ceoq:e W. Kninghton: Power Plant located in San Luis Obispo. Washington.D.C.20555. ATTN: petitioner's name and telephone California. Docketing and Service Branch. number: date petition was mailed; plant in accordance with the licensee's By September 19.1983, the licensee name; and publication date and page application for amendment dated July may file a request for a hearing with number of this Federal Register notice. 19.1982 and supplementalletter dated respect to issuance of the amendment to l A copy of the petition should also be October 12.1982, the amendraent would the subject facility operating license and sInt to the Executive Legal Director, modify the Diablo Canyon Nuclear any persons whose interest may be U.S. Nuclear Regulatory Commission. Power Plant Physical Security Plan to affected by this proceeding and who Wr shington. D.C. 20555. and to Phillip eliminate certain vital access controls wishes to participate as a party in the A. Crane Jr Esq., Pacific Cas & Electric that exceed current regulatory proceeding must file a written petition Company. 77 Beste Street. San requirements. for leave to intervene.%e request for a Francisco. California 94106 and Norton. Befure issuance of the proposed hearing and petitions for leave to Burke. Berry & French P.C ATTN: Bruce license amendment the Commission intervene shall be filed in accordance Norton. Esq 2002 East Osbom Road, will have made findings required by the with the Commission's ** Rules of l l
i 1 ) t Federal Register / Vol 48. No.101 / Thursday. August 18. 1983 / Noticca 37555 Practice for Domestic Licensing determination on the issue of no Nuann. Esq. 2002 East Osborn Road. Procecdings"in 10 CFR Part 2. lf a significant hazards consideration. The Phoenix. Arizona.850tG attorneys of the request for a hearing or petition for final determination will serve to decide licensee. less e to intervene is filed by the above when the hearing is held. Nnntimely filings of pctitions for leave date, the Commission or an Awnic If the final determination is that the to intervene, amended petitions. Safety and Licensing Board, designated amendment request involves no supplemental petitions and/or requests by the Commission or by the Chairman significant hazards consideration. the for hearing will not be entertained of the Atomic Safety and Licensing Commission may issue the emendmenu absent a determination by the Board Pawl, will rule on the request and make it effective, notw ithstand,ing Commission. the ;ncsidmg officer or the e.d/or peii. ion and the Secretary of the the request for a hearing. Any heanng Atomic Safety and Liensing Board darignated Atomic Safety and Licensing hcid would take place after issuance of designated to rule on the petitinn and/or Donrd willissue a notice of hearing or the amendment. re st, that the petitioner has made a an appropriate order. If the final determ.inattun is that the substantial showing of good cause for As required by 10 CFR 2 714. a amendment m, solves a sigmficant the granting of a late pehtion and/or a petition for leave to intervene shall set hczards consideration, any hearing held request. This determir.ation w di be forth with particularity the mtcrest of would take place before the issuance of based uPon a balancinS of the factors the petitioner in the proceeding, and any amendment. how that interest may be affected by the Normally, the Commission will not specified in 10 CFR 2.714(a)(1) (i)-(v) results of the proceeding.The petition issue the amendment until the and 2.714(d). shot.td specifically explain th; reasons expiration of the 30-day notice period. Dated at Bethesda htaryland. this 1tih day why intervention should be permitted Ilowever, should circumstances change of August.19si with particular reference to the during the notice period such that failure For the Nuclear Regulatory Commission. following factors:(1)The nature of the to act in a timely way would result for George W. Knighton, petitioner's right under the Act to be example,in derating or shutdown of the c37,f, gjc,,,j,,3,,,,3 g,.,, gj, j,j,,,f made a party to the proceeding:(2) the facility, the Commission may issue the tjc,,,j,g. nature and extent of the petitioner's license, amendment before the m,,,,, g property, financial, or other interest in expiration of the 30-day notic,e penod. the proceeding; and (3) the possible provided that its final determmation is effect of any order which may be that the amendment involves no entered in the proceeding on the significant hazards consideration.The petitioner's interest.The petition should final determination will consider all PACIFIC NORTHWEST ELECTRIC also identify the specific aspect (s) of the public and State comments received. POWER AND CONSERVATION subject matter of the proceeding as to Should the Commission take this action. PLANNING COUNCIL which petitioner wishes to intervene. It will publish a notice of issuance and Any person who has filed a petition for provide for opportunity for a hearing Fish Propagation Panel; Meeting leave to intervene or who has been after issuance. ne Commission expects { Qa on amlo th' admitted as a party may ' mend the that the need to take this action will a 9.,, d petition without requesting leave of the occur very infrequently. Board up to fifteen (15) days prior to the A request for a hearing or a petition Conservation Planning Council first prehearing conference scheduled in forleave to intervene must be filed with (Northwest Power Planning Council). the proceeding, but such an amended the Secretary of the Commission. U.S. Acnon: Notice of meeting to be held petition must satisfy the specificity Nuclear Regulatory Commission, pursuant to the Federal Advisory requirements described above. Washington. D.C. 20555. Attention: Committee Act. 5 U.S Appendix 1.1-4; Not later than fifteen (15) days prior to Docketing and Service Branch, or may correction. Activities willinclude: the first prehearing conference be delivered to the Commission's Public
- Approval of minutes scheduled in the proceeding, a petitioner Document Room.1717 H Street. N'W, shall file a supplement to the petition to Washington. D.C. by the above date.
- Panel discussion on pnontization intervene which must include a list of Where petitions are filed during the last (working session) the contentions which are sought to be ten (10) days of the notice period, it is
- Panel discussion on Bonneville's litigated in the matter, and the bases for requested that the petitioner promptly so proposed procurement process for FY each contention set forth with inform the Commission by a toll free 1984 (working sesion) r reasonable specificity. Contentions shall telephone call to Western Union at (800) be limited to matters within the scope of 325-6000 (in Missouri (000) 342-6700).
- Oth'.'
the amendment under consideration. A The Western Union operator should be
- Public comment
( petitioner who fails to file such a given Datagram identification Number Status: Open. supplement which satisfies these 3737 and the following message requirements with respect to at least one addressed to George W. Knighton:
SUMMARY
- His document corrects a contention will not be permitted to petitioner *a name and telephone meeting notice for the Fish Propagation participate as a party.
number. date petition was mailed: plant Panel that appeared at page 34823 in the Those permitted to intervene become name; and publication date and page Federal Register of Monday. August 1 parties to the proceeding, subject to any number of this Federal Register notice. 1983 l48 FR 148). The action is necessary limitations in the order granting leave to A copy of the petition should also be to correct the meeting date and contents. intervene, and have the opportunity to sent to the Executive legal Director, participate fully in the conduct of the U.S. Nuclear Regulatory Commission, oAm August 29.1983. 9.30 a.m. Correction.. nearing. Including the opportunity to Washington D.C.20555 and to Philip A. present evidence and cross-examine Crane Jr Esq., Pacific Cas & Electric AOoRESS:De meeting will be heId in witnesses. Company,77 Beale Street. San the Council's Public Meeting Room at If a hearing is requested. the Francisco California 94106 and Norton. 700 S..W. Taylor Street. Portland. Commission will make a final Burke. Derry & French P.C. Attn: Bruce Oregon. ,,. _., + _ _ Q
3' Federal Register / Vti 48. Ns.161/ nursd.y. August d.1983 / Notices 37551 4 ,e telephone number):(date petition was (1980).The address cf the new Board considered not likely to involve mellad);(Cosnail University); and memLaris: Administrative Judge significant hazards consideration (48 FR (publ dats and page number of :- Frederick J. Shon, AtomicSafety and 14870). One such example is (1) a purely thisF Radstermotice). A copy of' Licensing Board. U.S. Nuclear administrative change to technical the petition eleould also be sent to the + Regulatory Commission. Washington, specifications; for example, a change to Executive Legal Director. U.S. Nuclear D.C.20655. -. achieve consistency tluoughout the Regulatory Cosimission.-Washington. ' Inued'st Bethuda. Marfland, this 12th day Technical Specifications, correction of D.C.20655 and to Dean Paul Metamme of Angust sees.- an error, or change in nomenclature. College 'of C -i,. Carpenter Hall. B. Paul comer. )r, Another such example is (ii) atchange Cornell University. Ithaca, New York. cy,j,fagmfojamffy,yjg,,aromjeg,f,fy that constitutes an additionallimitation. Nontimely filings of petitions for leave anducensingsoardPeel. restriction, or control not presently to intervene, amended petitions. u,, m,ag u..g included in the technical specifications; supplemental petibons and/or requests , _ *_ _ rois.es.g for example, a more stringent for hearing will not be entertained I surveillance requirement. absent a determination by the 1/ The Licensee is installing a post-Commission, the presiding officer or the hDocket No. 50-2751 s Accident Sampling System in rufeot efiti d/or Pacific Gas & Electric Co.; compliance with license condition e Ig ted request that the petitioner has made a Consideration of lesuance of 2.C(8).h. This h, cense condihon was substantial showing of good cause for Amendment to Focility Operating imposed by the NRC staff to upgrade the the granting of a late petition and/or t.icense and Proposed No Significant post-accident samplying system in request.That determination will be Hazardsf Consideration Determination accordance with NUREG-0737. It based upon a balancing of the factors and Opportunity for Hearing requires &c instapon o(six containment isolation valves. These six speci7;ed in to CFR 2.714(a) (1)-(v) and %e U.S. Nuclear Regulatory - valves and one other valve have been i 2.714(d). Commission (the Commission)is identified as subject to localleak rate For further details with respect to this considering issuance of an amendment action, see the application for renewal to Facility Operating Ucense No.DPR-testing. in accordance with Appendix J to 10 CFR Part 50 and must be added to dated May 27.1980, as supplemented on 76, issued to Pacific Cas & Electric Table 3.6.1. An additional three check September 15.1980, which is available Company (the licensee). for operation of valves have also been identified as forpublicinspection at the theDiabloCanyon Unit 1. Nuclear being. subject to Appendix J leek testing Commission's.Public Document Room at Power Plant located in San Luis Obispo and are designated a' s suctrin Table 3.6-1717 H Street NW., Washington, D.C. California' osed'amendme'nt would'
- 1. Two isolation valves are also being 20555(d dt Bethesda, Maryland this 12th day, Date
~ '. The prop result in certain changes to Table 3.6-1 removed and the penetration willbe (Containment Isolation Valves) of the closed with cape welded into the pipe , f AugusM9e3. '; o penetration.ne function of thsee/ For the'Naclear Regule' tory Commtmalon. facility Tpchnical Specifications. nese valves have been replaced by bdrogen codi o.'thoussa.'.' - chief standardisa:Es%,,, t rh a ngas reflect proposed motainmant recombiners and therefore since the - isolation systpm modiScations, an'... d PSpecialpigacss entaffadding several y,gy,,,g being'removled any refemace ,,;w smncAg/pfs/en',ofucenang. , ~' - deleting others. and rvalves to the tabl< to them in Table 5.6-i nmst be deleteil. puner es.asmahds's.eames g _ evising ihe;. 1 footnoting in the tablelin accordance n Additionally, thirteen valvis will be , q. ausea,,cc.onseg:e.i as . m .m -3 ;, e, with the W'a application dated e subject to admfnistrative control.'which g gggg gg l IDo (ASCAP Nel77-i re ma a of tlie pro as samp%d NW a H 347-cis 0141 * - license amendment.'the Comminaion nigned as such in taw 3MA xn r have made Enengs mquimd by the thirteen valves consist of the six new c w ' Long toland Lighting Co., Shoreham Nuclear Power Station. Unit 1 Atomic Energy Act of1954. as amended containment isolation valves mentioned above and seven valves which are Construction Permit No.CPPR-96; I *ACI*"d currently listed in Table 3.6-1 but which Reconstitution of Board "8.g ,"mminion b made a pmposed are inadvertenly not designa.ted as being Parsuant to the authority contained in determination that the amentiment subject to administative control. 10 CFR 2.721 (1980), the Atomic Safety request involves no significant hazards Without such designation, operation of and Ucensing BoanflorLongIshmd. consideration. Under the Comminalon's these valves for sampling purposes u hfing Coaqpony(Shoreham Nucleat regulations in 10 CFR 50.92, this means w uld violata the Technical s Power Station. Unit 1). Docket No. 50-that operption of the facility in. Specifications. ,s 322-Oi,-a. is hereby reconstituted by. 'accordance with the proposed ' v. The proposed amendment reflects an appolating McJrederick J. Shan to the a amendriant would not (1) involve a upgraded post-accident samplying, + Board in pleos of Dr;M. Stanley ? ' - signdicant increase in the probability or - bystem. provides for consistency in the. Uvingston, who is presently unable to consequenosebf an accident previously Technical Specifications, permits tasting continue ble service on the Board. evaluated; or (2) cmets the pan = amity of during normal routine plant activities. As reconstituted. the Board is e o '. a new or diffstent kind of accident frosa ; conforsas alors securately to the... comprised of the foBdwing& % =#E ' any eccident previouslygralsh4=rl' ar(3) iproi '-- % ~ 1 5 E pert. t Administrative Judges:Jamnes Ad n.... Involve a significantr=d=reinerth sk.. 50/and.la MMese built Laurenson.;Chainnan Dr. Jerry R,Kline;, marsia of safety. ? *.frms n conditionof theplants py,. e Mr. Frederick'J. Shon. ' ~ neCommission has provided. f6 i nerefow, based on these. f - All correspondence. documents and guidance for the application of the considerations and the thrge criteda t , other matdrialshallte Bled with the '.S criteriain10 CPR50.ag by providi g given in the Ibtertt>peregraph above. we, y Boardin acconlance with toCFIYtrof&' examples ~of amendments that are," - have madelproposed determination ; O l l l
3 ~ b 37552 Feder'l Register / V:1. 48. N:< 161/ Thursdry. Augs 18..'Wr/ Notiers that this amendment request involves no the proceeding, but such an amended the Secretary of the Commission. U.S. significant hazards consideration... petition must satisfy the specificity Nuclear Regulatory Commission. De Commission is seeking public-requirements described above.. Washington,D.C.20555. Attention:
- comments on this proposed.,.y a Not later than fifteen (15) days prior to-Docketing and Service Branch, or may datermination. Any comments receivaid, the first prehearing conference be delivered to the Commission's Public '
within 30 days after the'date of,.. scheduled in the proceeding. a petillorier Document, Room.1717 H Street NW., ~ publication of this notica will.be. f shall file a supplement to the petition to Washington. D.C. by the above date.' considered in making any final Intervene which must include a list of Where petitions were filed'during the ~ detennination. %e Commission will not the contentions.which are sought to be, last ten (10) days of the notice period, it normally make a final determination litigated in the' matter, and the bases for is requested that the petitioner promptly unlest it receives a request for a each contention set forth with so inform the Commission by a toll free heanng. reasonable specificity. Contentions shall telephone call to Western Union at (800) Comments should be addressed to the be limited to matters within the scope of 325-6000 (in Missouri (800) 342-6700). . Secretary of the Commission. U.S. the amendment under consideration. A He Western Union operator sho_uld be Nuclear Regulatory Commission, petitioner who falls to file such a given Datagram Ider1tification Number Washington. D.C. 20555. ATIN: supplement which satisfies these 3737and the following message Docketing and Service Branch. requirements with respect to at least one Dy September 19.1983, the licensee contentloh will not be permitted to addressed to George W. Knighton: Petitioner s name and telephone may file a request for a hearing with participate as a party. respect to issuance of the amendment to Hose permitted to intervene become number; date petition was mailed; plant the subject facility operating license and parties to the proceeding, subject to any name; and publication date and page any person whose interest may be limitations in the order granting leave to number of this Federal Register notice, affected by this proceeding and who intervene and have the opportunity to A copy of the petition should also be wishes to participate as a party in the participate fully in the conduct of the sent to the Executive Legal Director, proceeding must file a written petition hearing, including the opportunity to U.S. Nuclear Regulatory Commission, for leave to intervene. %e request for a present evidence and cross-examine. Washington. D.C. 20555. and10 Phillip hearing and petitions forleave to witnesses. A. Crane Jr Esq., Pacific Gas & Electric intervene shall be filed in accordance if a hearingis requested.the Company 77 Beale Street. San with Commission's ** Rules of Practice Commission will make a final Francisco. California 94106 and Norton.. for Domestic Licensing Proceedings" in, determination on the issue of no Burke. Berry & French P.C A'ITN: Bruce 10 CFR Part 2. If a request for a hearing - significant hazards consideration. He Norton. Esq 2002 East Osborn Road.. or petition for leave to intervene is filed final determination will serve to decide Phoenix. Arliona 85018 attorneys for, ~ by the above date, the Commission or when the hearingis held. s ' an Atomic Safetysnd Licensing Board.- If the finaldetermination is that the.. the licensee; -w Nontimely filings of petitions for leave designated by the Commission or by the amendment request involves no. 'tlie -to intervene, amended petitions. ku'est Charimanof.the Atomic Safety and, significant hazards conalderation. supplemental petitions and/or re Licensing Board Penal, will rule on the Commission may issue the amendment for hearing will not be entertained and make it effective, notwithstanding i absent a determination by thel. Y , request and/or petitica and the, < v Secretary or the.desig sated Atomic.. the request for a hearing."Any heahng ". Commission, the presiding ofBceFor tha' Safety and Licensing.soard will issue a held Would take place aftir issuance of ' Atomic Safety and Licensing'Bosird notice of hearing pr an appropriate the amendmentT ' ~ v ~*e
- a...w If the Analdeterminationis that the. des gnated to rule on the petition and/or order.,<_.,..
request, that the petitloderliasinade a As reqsired by'fo'CFR I 2.714. a1.. t amendmentinvolves a significantM - substantial showing of good cause for~' petition for leave to intervene shall set ' hazards consideration, any hearing held the' granting of a late petition and/or - forth with particularity the interest of would take place before the issuance of request.ne determination willbe 'U the petitioner in the proceeding. and any amendment. based u n a balancing of the factors how that interest may be affected by the Normally, the Commission will not specified in to CFR 2.174(a)(1) (IHv) results of the proceeding.ne petition issue the amendment until the should specifically explain the reasons expiration of the 30 day notice period. and 2.714(d). why intervention should 6e permitted However should circumstances change For further details with respect to this - with particular reference to the .during the notice period such that failure action, see the application for amendment dated May 2.'1983. which l fo!!owing factors:(1)He nature of the to act in a timely way would result, for , available for public inspection at the, s petitioner's right under the Act to be example, in derating or shutdown of the made a party to the proceeding: (2) the^ facility. the Commissioninay issue the Commission's Public Bocument Room, nature and extent of the petitioner's license amendment before the 1717 H Street NW., Washigton. D.C.' property, financial, or other interest in expiration of the 30 day notice period, and at the California Polytechnic State the proceeding: and (3) the possible - provided that its final determination is University Library. Documents and-effect of anyorder which may be% >. that the amendmentinvolves noe c. Maps Department. San Luis Obispo '.s. entered in the proceeding on the m M significant hazards considerstion,%e. California 93407.. .'4f petitioner's interest. He petition should final determination will consider all - Dated at Bethesda, Maryland,"this 11th day ^m also identfy the specific aspect (s) of the - public and State comments received. - subject matter of the proceeding as to
- Should the Commidalon take this action., of August.sessy n..
which petitioner wishes to intervene. It will publish a notice of issuance and For the Nuclear Regulatory Commission. Any persons who has filed a petition for provide for opportunity for a hearing coarse w. Kalehten. leave to latervene or who has been:"? efter issuance.%e Commisalan e cy,lef, IJcenshy Smnch Na 3. cms /on of . admitted as e party may amend the 1 that the need to take this action uoensing. ',e ~ .]
- petiticis(without requesting leave of the., occur very infrequently.,.. vw u i
+' Board peille,. =t==.""" W**""l4 ' F 1,mee6aggng to fifteen (15) tiays prior to thei [for' leave to intervene anust be est b N. A request fora hearing ora first p ating conference pcheduled in ces l
4 I o [ Federal Register / Vol. 48. No.161 / Tht.rsdav. August 18.19m / Notices '37553 ( IDocket No. 50-275) change resulting from the applir.ation of roqunt fue a haring or petitinn fnr a small refinement of a previously used leave to intersene :s fiicd by the above Pacific Gas & Electric Co4 calculational model or designinethod. date, the Commission or an Atomic Con:Ideration of issuance of The Licensee is proposing to change Safety and 1.icensing Doard, designated Amendment to Facility Operating maximum response time for initiation of by the Commission or by the Chairman Licenso and Proposed No Significant containment spray from 27.5 seconds to of the Atomic Safety and Licensing Hazards Consideration Determination 48.5. The licensee performed an analysis Board Panel, will rule on the request and Opportunity for Hearing of the change in response time.The and/or petition and the Secretary of the The Lt.S. Nuc! car Regulatory results of the analysis indicated an designated Atomic Safety and Licensing Comminion (the Commission)is increase in contamment peak pressure. Duard willissue a notice of henring or considerir g issaarce of an amendment I"U wing a loss of-accident, from 40.65 an approguiate order. to F.s.ility Optrating Lictnse No. DPR. p6ig to 40 91 psig. The FSAR value of the As required by 10 CR 2.714 a 70 issued to Pacific Cas & Electric two-hour thyroid dose at the site petition for leas e to,ntervene shall set i Com;wr.y. (the 1;censee), for olieration of boundary was previously calculated to forth with particularity the interest of the Dir.blo Canyon. Unit 1. Nuclear he 95.9 REM for the car e of no post-the petitioner in the proteeding. and Power Plant located in San Luis Obispo. LOCA delay m the containment spray. how that in! crest may be affected by the California. The licensee has reanalyzed the above results of the proceeding.The petition The proposed amendment would value and the value for the proposed should specifically explain the reasons change the response time for delay m containment spray using a why intersention should be permitted current verified code and dose with particular reference to the containment spray initiation in Table 3.3-$ of the Facility Technical c nversion factors provided in Revision following factors:(1)The nature of the 1t Regulatory Guide 1.109. The results petitioner's right under the Act to be Specifications from equal to or less than 27.5 seconds to equal to or less than 48.5 of the reanalyses mdicate that two-hour made a party to the proceeding:(2) the seconds. As a result of this change, thyroid does at the site would be 85.6 nature and extent of the petitioner's Sections 3.3.2, 3.4.6.1.4. 4.8.1 and Table RW for no spray delay and 93.4 REM property, financial, or other interest in 4.8-2 of the TechnicalSpecifications f r the proposed delay. While there is a the proceeding; and (3)'the possible would have to be updated to reflect this small reduction in the safety margin in effect of any order which may be change in accordance with the both containment presssure and dose entered in the proceeding on the consideration on the basis of the Licensee *s submittal dated June 23,1983 petitioner's interest.The petition should and supplementalletter dated July 26 analysis using the revised code, they are also identify the specific aspect (s) of the clearly within acceptable criteria,i.e. subject matter of the proceeding as to 3933' fore issuance of the proposed Be the design of the containment. 47 psig-which petitioner wishes to intervene. and the 300 REM value in 10 CFR Part license amendment.the Commission Any person who has filed a petition for 100. leave to intervene or who has been will have made findings required by the Themfom, based on these Atomic Energy Act of 1954, as amended admitted as a party may amend the c nsideratians, and the thne en.teria (the Act) and the Commission petition without requesting leave of the given in the fourth paragraph above, we Board up to fifteen (15) days prier to the regulations. have made a proposed determmation The Comm.ission has mde a proposed firat prehcaring conference ocheduled in determination that the amendment that this amcodment request involves no the proceeding. but such an amended significant hazards consideration. request mvolves no significant hazards The Commissinn is seeking public petition must satisfy the specificity requirements described above. consideration. Under the Commission's comments on this proposed regulations in to CFR 50.92, this means. determination. Any comments received Not later than fifteen (15) days ' prior to that operation of the feality in w thin 30 days after the date of the first prehearing conference accordance with the proposed publication of this notice will be scheduled in the proceeding. a petitioner amendment weald not (1) involve a considered in making any final shall file a supplement to the petition to sigmficant inciease in the probability or determination. The Commission will not mtervene which must include a list of consequences of an accident previously normally make a final determination the contentions which are sought to be evaluated; or (2) create the possibility of unless it receives a request for a litigated in the matter, and the bases for a new or different kind of accident from hearing. each contention set forth with any accident previously evalauted; or (3) Comments should be addressed to the ressonable specificity. Contentions shall r involve a significant reduction in a Secretary of the Commission, U.S. be limited to matters within the scope of margin of safety. Nuclear Regulatory Commission, the amendment underconsideration. A The Commission has provided Washington, D.C. 20555, ATI'N: petitioner who fails to file such a guidance for the application of the Docketing and Service Branch. supplement which satisfies these L criteria to 10 CFR 50.92 by providing By September 19.1983, the licensee requirements with respect to at least one examples of amendments that are may file a request for a hearing with contention will not be permitted to considered not likely to involve respect to issuance of the amendment to participate as a party, significant hazards consideration (48 FR the subject facility operating license and Those permitted to intervene become ~ 14870). One such example is (vi) a eny person whose interest may be parties to the proceeding, subject to any change which either may result in some affected by this proceeding and who limitatinns in the order granting leave to increase to the probability or wishes to participate as a party in the intervene. and have the opportunity to consequences of a previously. analyzed proceeding must file a written petition participate fully in the conduct of the accident or may reduce in some way a for leave to intervene.The request for a hearing. including the opportunity to safety margin, but where the results of hearing and petitions for leave to present evidence and cross. examine the change are rJearly within all intervene shall be filed in accordance witnesses. acceptable criteria with respect to the with the Commission's " Rules of If a heanngis requested,the system or component specified in the Practice for Domestic Licensing Commission will make a final Standard Review Plan: for example, a Proceedings"in to CFR Part 2. If a determination o i the issue of no
s ( f. oQ 3',534 Tederal Regleter / Vol. 48. No.1ot / Thursday. Atigust 18, 1983 / Nntices quif.o.mt hazards consideration.The Phot nix. Arizona 85016. attorne)s for Atomic Energy Act of 1934. as amended final determination will serve to decide the licensee. (the Act) and the Commissinn's when 'he hearing is held. Nontimely filings of petitions for leave regulations. If the final determination is that the to interver.e. amended petitions. The Commission has made a proposed i.ciendment reque st involves no supplement.1 petitions and/or requests deterrhination that the amendment sigrdficant hazards consideration the for hearing will not be entertained requt:st involves no significant hazards Comn:ission may issue the amendm...t absent a determination by the consideration. Under the Commission's and make it effective. notwithstanding . Commission, the presiding officer or the regulations in 10 CFR 50.92, this means !!.e rept for a ha ating. Any hearing Atarr.ic Safety and Ucensing Board that operation of the facility in b'd v.t.cl.! tr.ke p!are after issuance of designated to rule on the pi tition and/or ccenrdance with the preposed
- he a
.t adment. request that the petitioner has made a amendment would not (1) involve a C ---- If the fir.:! defstn@& tion is that the si.bstantial showing of good cause for signif r nt increase in the probcbility or ,:nendrnent intohes a rigr.ificant the granting of a late petitioner and/or cor:sequer.t.es of an accident previously hn:.rds ennsider:. tion. any hearing held request. The deter..ination will be n ulnated. or (2) create the pessibility or wuld take place before the ismance of bued upon 4. ba!ancir.g cf the factors a new different kind of accident from eny ament
- nent.
specified in 10 CFR 2J14(a)(1)(i)-(v) and any accident paviously ew!nated; or (3) Normellt, the Commission wi!! not 2.174(d). invols e a significant rcduction in a issue the arrendment until the For further details with respect to this margin of safety. expirati. n of the 30-day notice period. action, see the application for The Cnmmitsion's proposed liowen.Would cirrumstances change amendment dated June 23.1983. and determination is based on its finding during I a notice penod such that failure supplemental information dated July 28 that the revised Ph sical Security Plan 3 to act it. 4 timely way would result for 1983 which are available for public would continue to meet tne general and exan.pl. In derating or shutdown of the inspection at the Commission's Public specific requirements of the regulations fr.cility. Jie Commission may issue the Document Room.1717 H Street. NW on physical security contained in 10 CFR license r.mendment before the Washi,gton. D.C. and at the California 73.55 (b) through (h) and could improve expiratic n of the 30-day notice period. Polytechnic State University 1.ibrary. access to vital equipment where ci short providet that its final determination is Documents and Maps Department. San response time is essential.This that the amendment involves no Luis Obispo.C lifornia 93407. amendment will delete the use of certain sigmficant hazards consideration. The final determination will consider all Dated at Bethesda, Maryland, this 12th day internal controls that are not mandated of August. :983. by regulatory requirements for access to certain vital areas. Moreover. no other e tb action. For the Nuclest Regulatory Commission. uld the mis n nuc! car power plant in the United States it will publish a notice ofissuance and Georse W. Kaishtoa. of America contains the above cited provide for opportunity for a hearing Chief ucensing Brench No. J. Division of requirement that the licensee proposes after issuance. 'Ilie Come.ission expects ucensing. t delete.The bases for the staffs that the need to take this action will inonosmeanw m-na mi determination that the proposed occur very infrequently. onimo cons rsso-et-as amendment involves no significant A request for a hearing or a petition hazards consideration has been for leave to intervene must be filed with 10 chet No.50-2751 documented: however,it is being e Secretary of the Commission. U.S. withheld from public disclosure th,uclear Regulatory Commission..Pacific Gas & Electric Co4 N pursuant to 10 CFR 73 21' king public Washington, D.C. 20555. Attention: Consideration of issuance of The Commission is see Docketing and Service Branch, or may. Amendment to FacitPy Operating comments on this proposed Ucense and Pmposed No Significant determination. Any comments received ocu nt Roo 7 S reet. W., pu ca n f a lee i p i o s were fi ed ng e H ai"9 considered in making any final last ten (10) days of the notice period,it is requested that the petitioner promptly The U.S. Nuclear Regulatory determination. The Commission will not i so inform the Commission by a toll free Commission (the Commission)is normally make a final determmation l tilephone call to Western Union at (800) considering issuance of an amendment unless it receives a request for a l 325-6000 (in Mis souri (800) 342-6700). to Facilit Operating Ucense No. DPR-hearing The Western Union operator should be
- 78. Issue to Pacific Cas & Electric Comments should be addressed to the given Datagram identification Number Company (the Ucensee), for operation of Secretary of the Commission. U.S.
3737 and the following message the Diablo Canyon. Unit 1 Nuclear Nuclear Regulatory Commission. eddressed to George W. Kninghton: Power Plant located in San 1.uls Obispo. Washington. D.C. 20555 ATTN: petitioner's name and telephone California. Docketing and Service Branch. number: date petition was mailed; plant in accordance with the licensee's By September 19.1983, the licensee name; and publication date and page opplication for amendment dated july may file a request for a hearing with number of this Federal Register notice. 19.1982 and supplemental letter dated respect to. issuance of the amendment to A copy of the petition should also be October 12.1982, the amendment would the subject facilitv operating license and s;nt to the Executive Legal Director, modify the Diablo Canyon Nuclear any perse-8e.terest may be U.S. Nuclear Regulatory Commission. Power Plant Physical Security Plan to affectr ' ..,,wceed.ng and who Washington. D.C. 20555. and to Phillip eliminate certain vital access controls wishe; "cipate as a party in the A. Crane Jr Esq., Pacific Cas & Electric that exceed current regulatory proceeuing must file a written petition i Compiny. 77 Beale Street. San requirements. for leave to intervene.The request for a Francisco. California 94108 and Norton. Defure issuance of the proposed hearing and petitions for leave to Burke. Derry & French P.C ArrN: Bruce license amendment, the Commission intervene shall be filed in acentdance Norton. Esq.,2002 East Osbom Road, will have made findings required by the with the Commission's ** Rules of
c ,:.,;ss l'ederal Register / y ' 4H No.170 / Wedt esd,n. Aue.s: :ll.( } / Nos es -~- .i ] Ngnm Nuclear Power Station located in n.%re and extent of the pet tioner's D C. 20555. and to W. S Ston e Eng.. Plymouth County Massachusetts. property, financial, or other mterent.n Boston Ednon Company. 800 Do.s1ston The amendment would revise the the proceeding. and (3) the possible Street. 36th Floor. Doston. ~ operating license and the provisions in effect of any order which may be Massachusetts 02199. attorney for the the Technical Specifications relating to entered in the proceeding on the licensee. changes to permit reactor operation at petitioner's interest. The petition should powerlevels in excess of 70% of rated also identify the specific aspect (s) of the Nontimely fdings of petitions for leave pew er with one recirculation loop out of subject matter of the proceedinF as toto intervene, amended petit:ons. senice. Presently, the Pdgrim operating which petitioner wishes to intertene. supp!emental pet:tions and/or requests hu nse requires plant shutdown if an ~ idle recirculation loop cannot be Any person who has fi:ed a petition 'or for hcann;; wiS not be enter:an.ed 3 leave to intervene or who has been absent a determination bv the returned to service within 24 hours. The chonpe proposed by the license would adrnitted as a party may amend the Commission. the presidm's offic.er or the petition withoa: reyesung leave of the Atomi: Safets and Licens.nc So rd delete inis license condition and modify Board up to fifteen (15; days prior to the desipated to' rule on the pet:t.on and/or the Technical Specifications (TSs) as first prel. earing conference schedded in request. that the petitioner has rnade a necessary to provide for appropriate the proceed:ng. but such an amended substantial showmg of gaod cause for Ase%Fe Pcwcr Range Monitor (APRM) flux scram trip and rod block settmgs, petition must satisfy the specificity the grant.ng of a late perinon und/or reccirements described above. regaesi. That dr!ermination w ill be an ircrease in the safay limi! M:n: mum Not later then fif:een (15) cays paor to ba d. pn a ba:ancing of the f..nors Cr.tical Pcw er Ratio tMCPR) value and the first prehear:ng conference spec f ed m to CFR 2.714(a)(1)Di-bi cc rei;sians to the allowab:e Aserage scheduled in the procceding a pet::ioner 14(d)~ ~ P; ann Linear Heat Cer.oratan Rate (APLHCR) salaes sunaMe for use with shall file a supplemen: to the petition to For funbr deta::s wnh respec: to :Ns an id:e recirculation lor p. in accordance mtervene which must include a hst of "" "" su the appheation for the contentions which are amendmon: dated May 12.1ust w hvh m wch the hcensee's apphcotion for sought to be htiga:ed in the mat:er. and B asag.Ne for rubhc inspect:an at the anc.dment dated May I.1981. the bases for each contention set for:h Commission's Public Documen: roem. Prior to issuance ol'the proposed with reasonable specificity. 1717 H Street. NW.. Washireton D C. license amendment. the Commission Contentions shall be limited to and at the Plymouth Public Library. will base r ade Lndings required bv the matters within the scope of the North Street. Plymouth. Massachusetts. Atomic Energy Act of 1954. as amended amendment under cons;deration. A 02360. (the Act) and the Commission's petitioner w hu fails to file such a s er2ations. supplement which satisfies these Dated at Bethesda Mar land :h s Odd d of Augast.1983 4 'Br September 30,1983. the lir ensee requirements with respect to at least may ble a request for a hearing with one contention will not be permitted For the Nudcar Regulatory Cun..r.~n respect to issuance of the amendment to to paMicipaN as a party. Robert A. Hermann. the st.bjec! facility operating license.nd ThCse permitted t0 in:ETs One beCome , 7m....',g,,. .4rr.cc Ch O.v ct-. Reart. n F 1 an) person whose interest rnay be part.es to the proceeding. subject to unt aficcted by thir proceed:r.g und who pmitations in t(.e craer gren:ing Icas e to wishes to participate as a party in the intervene. an-nase the opportunity to proceeding must file a written petition present evidence and cross.exartme for leave to intervene. Request for a w tnesses. hearing and petitions for leave to A request for a hearing or a petition IDocket No. 50-2751 intervene shall be filed in accordance for leas e to intervene shall be filed with with the Commission's " Rules of the Secretary of the Commission. United Pacific Gas and Electric Co.; Practice for Domestic Licensing States Nuclear Regulatory Commission. Consideration of tasuance of i Proceedings"in 10 CFR Part 2. If a Washington. D.C. 20555. Attention: Amendment to Facility Operating request for a hearing or petition for Docketing and Service Branch. or may License and Proposed No Significant leave to intervene is filed by the above be delivered to the Commission's Public Hazards Consideration De. mination date. the Commission or an Atomic Document Room.1717 H Street. NW, and Opportunity for Hearing Safety and Licensing Board. designated Washington. D.C. by the above date. The U.S. Nuclear Regulito[y by the Commission or liv the Chairman Where petitions are fded during the last Commission (the Cornmission)is i of the Atomic Safety and' Licensing ten (10) days of the notice period. it is considermg issuance of an amem!nwnt B.u:d Panel. will rule on the request requested that the pet.itioner or la Facility Operating License No UPR-and/or petition and the Secretary or the representatis e for the petitioner
- 76. issued to Pacific Cas and Elec tric deCp.tt d Atomic Safety and Licensing.
Board willissue a notice of hearing or promptly so mform the Commission by a Company (the hcensee). for operation of toll free teicphone call to Western the Diablo Canyon. Umt I nuclear an appropriate order. Union at (800) 325-6000 (in Missoun power plant located in San Luis Olnspo As required by to CFR :.714. a (8001342-6700L The Western Union County. California. petitien foi leave to mtervene shall set cperator should be given Datacram The propc3rd amendment waald - for:h with particularity the interest of Idenufication Number 377 and the update the fonh:3 Techmcal the protioner in the protecding. and fol: ewing message addressed to Specificatens to re Crct the ins.J!.itien hcw that interest rnay be affected bs the Domenic B. Vassallo:Ipetitioneri nameof an additional:500 :pm firewater resdis of the proceedirg. The petition and telephone numbeth (date petition pump to proside an increased c, w.tv. i would specifica!!y esp:am the reasons was mailed): (p'.Lnt name); and based on a reanalysis of the larr<: hre n Fr mterunt;on should be permitted (pt.bhcation datt,nd page number of sptem demand. e-d modify the d with particular reference to the this Federal Register notice). A cop 3 of surveillance. qui;ements for est% e lo!!awmp factors:(1) The nai ofthe the petition should also be sent to the mitiators in the Halon fire supprm.on 1 I pe'itior:er's right under the Act to be Esecutive Legal Director. U.S. Nuclear ss stem in accordance with the ho rnwe s t ade a party to the prorcedine. (2) the Reputatory Cemr iss:nn WasNrpton. Ippheation dated May 23.1083 f =_ d +. b
f' ,'] ) s U FederaliRegister / Vol. 48,.N.pd /UVednesday,. August 31, inaN/Wotic ... m.n posed M, E ndlSal . Before, - a..###Nammr+1,r... y.talaual==%. follawM. 4 .c-g TiW .u.: kT2 ge wir \\v',,M g f 1 k (Das such exasn'plqis;lechnica. i naturaandexten%6Ltba' etidoner' apure
- 8F-madeaphtjileM' '
nisfssve change ta.the p) l, M ) f dN. .l. Specificati_onspayj a v acidene <*a9 acy tirougio,changajo,i p ' TecdSpeciBoadon.a w,MiuacIt. ;agordai a propa-tygRa.W 1.t r-theproceeding;(3}Motheelitersh .t. uUhe .if. termination 44t' anG tp. q e twnminalon thd goer,!hlaeffesto i an errog &aWangiinnomenclahwe procieding.on the petitida'efs.lateresQm request involve & nas h'a_zards' -) consideratjo(Undir Cnminission's' . Tha'groposed amendment ia to correct..%4'p'etition sfiould pIs3 L an error m the i:urrent Lchnical' ) regulations frt10yF,R, '30.92 this mesna'. Specification which requires ;, of theprocec' ding as to iehicitjie'lltion' s specific asl dct(s)'ofthe subject mattIt : i that operat amendmenhym)fd not (1) involve, q ",.accordance,tonef tngr facility wisEps hilatervend. Any ~pecean~who " e yrit!$tbepfoposed, a remainirg. service life of at least 5 . ha Tilsd'a' petition forleaveJto intervena years whicalsnotcurrently technically '.. or:whohat een admitted a.; significagfncreabe in the probabilityor b feasible, since some period of time must consequences of an accident previously elapse from the moment of fabrication to may amend the petition with6ut ' ' evaluated or(2) create the possibility of installation at the facility. Therefore, requesting leave of the Board up to ' a new or different kind'of accident from based on this consideration and the : fifteen (15) days perior to the first any accident previously evaluated; or (3) three criteria mentioned above, we have prehearing conference schedufedfd th r involve a significant reductionin a mada a proposed da'armin='iaa thai.tha petitio@g, but such an amended proceedin margin of safety.: amendmantrequest stsatfidyhspecindtr 'i He Commission'has_ pro.iided' ". significant hazards cInyn!vas na%n. % ' requirements Bescribed'above' M - onsiderati'o guidance for the applicauon of these' cnteria by providing examples of , The Commission.isseekingpublic j; Not iater then fifteen (15J days p'r'for 'to the first preheering conference' 'N ' ".- comments on this proposed s amendments that are considered not, determination. Any comments received' scheduled in the proceeding, a petitf6ner l likely to involve a significant hazards within 30 days after the date al ' shall file a suppfement to the petitfon to ' consideration (48 FR 14870). One such inte in th ~ publicatidaplthis nntica willbeQ
- M[d aRetb cons, dered.In,manag any EnaG.g]L
., example is 's chqthet constitutee. arr ,,g 4.t & % i n thuiia d J.h" f Mrtions additionaMimi,tatfork restriction; org de terminatioi@firiaT determinafon 4 's Commissionwillnn control not' Technical 9)p,resentlyfacfuded fri the- - normally malle a and the basesfor ~eecircentention set '! ' k eciac' htronet for example, a unless it receives arequest foe a.83 fortliwith reasonablespeciNdfysQc7 more p _ilmendment which ' 'g-ilance requirement. hearingt e. ep.-! % +wr*/
- 1. gg 4. ContenHoes'shelT helimited fo n 13e'proposse
-Comments should beaddressed to the g p,q a increases the'reintred capacity of the - Secretary of the Commission U.S. > under considesadom'A netitlener wEo V 2 firewater system by mstalling a new fire NuclearRegulatmy f>== talon # g;ggg 4gy pump constitutes an additional-Washington,D.CM. Attn: Docketing [," 8" a A limitation that is currently required by and Service Branch / m. the Technical Specifications. n erefore, based on this consideration and the By September 30,198:L thelicensee n t be permiesdtopart>dyste as a l three criteria given above we have made may file a requestfor a hearingwith p d y-a proposed determination that this respect toissuance of the ammendment n sepernmNnmenebecome. { amendment request involves no to the subject facility operatinglicense parties to the proceeding, subject to any and any person whose interest may be limitations in the order granting leave to significant hazards consideration. affected by this proceeding and who intervene, and have the opportunity to Section 4.7.9.4c of the Technical Specifications currently requires that the wishes to participate as a party in the participate fully in the conduct of the explosive initiators in the Italon fire proceeding must file a written petition hearmg. including the opportunity to for leave to intervene. Request for a present evidence and cross. examine suppression system be replaced at least hearing and petitions for leave to witnesses. one every five years with initiators that intervene shall be filed in accordance if a hearings is requested, the have a remaining service life of at least with the Commission's " Rules of Commission will make a final 5 years. The licensee states that the Practice for Domestic Licensing determination on the issue of no greatest service life available for the Proceedings"in 10 CFR Part 2. If a significant hazards consideration. He type of explosive initiators used in the request for a hearing or petition for final determination will serve to decide flalon system is 5 years from the time leave to intervene is filed by the above when the hearing is held. i that they are made based on information date, the Commission or an Atomic If the final determination is that the obtained from the vendor. Consequently. Safety and Licensing Board panel, willamendment requestinvolves no j to meet the letter of the Technical Specifications replacement explosive rule on the request and/or petition and significant hazards consideration, the the Secretary or the designated Atomic Commission may issue the amendment initiators, which must have a remaining Safety and Licensing Board willissue a and make it effective, notwithstanding service life of atleast 5 years.is feasible notice of hearing or an apprgpriate the request for a hearing. Any hearing. only if zero time has elspeed from the order. held would take place after issuance ofs 1 time of manufacture.The proposed. As required by 10 CFR i 2JM."a the amendment.. s. - -8 M fi amendment request would require - replacement of the explosive irdliator petition far leave toiintervene sha11 sat if the finaldetermination is that the e prior to the expiration of ita servica lifa forth with particu!*rity thalataaest of amendment involves a significant and at least once every 5 years. . the petitionerin the proceedirs.and hazards consideration, any hearing held how that interest may ba affected by the would take place.before the issuspce of The Commission has provided. results of tha proceeding 'lha petition any amendment, guidance for the application of the should specifically explain the reasons Normally the Commission will not I g above mentioned criteria by providing why intervention should be permitted issue the amendment until the, examples of amendments that are with particular reference to the expiration of the 30-day notice period.
~ o 39540 Fedical RegistIr / Vol. 48. No.170 / Wednesday. August 31, 1983 / Notic s 1 Hosreverfahould circumstances change For further details with respect to this consequenes of an accident previously ,during the notice period such thatTallure action, see the application for evaluated: or (2) a new or differen. create the possibility of .ti act in m' timely way would result; for ' amendment dated May 23.1983, which' t kind of accident from A cxample,in deratligerelistdown4f thG u is'afallable for'giublicftsspection at the'. any accident previously evaluated; or (3) / ~ facility, the Commimaanh Q@sn'e~1ssaR$W Commission's Public Document Roonc involve a significant reduction in s' license amendmenth$ss M* 1717 H Street NW.; Washingtop6 D.C.g . margin of safety.. . s sxpiration of the 30 dsYnetice~p'e'riod.;. and the California PolytechnicStald.p" VNo cre'dit ts' takin..fot"oper6 tion o r 1 probidadlthalltilllRdeterinloatidn W' Oniversity Ubrary, Documentd a'ridf - main steani'lide re'diatio'n detectors in ~ thamiF"" '" iniolves nio % ? ' Maps Department, SariLuis Obispo. accident analyses.He staff proposes to / 0 ofghthcantliansr~dTconsideratf6:iflTe3 California 93407.* "j X *g's. determine that the proposed change to final determinationi will consider all i
- Dated at Bethuda. Maryland, this 2 th Alay the Main Steam Une Radiation-High public and State comments recelved."
of August 1983.
- 8elpoint involves no significant hazards Should the Commission take this action.
For the Nuc!est Regulatory Commission. consideration on the basis that the Main it will publish a notice ofissuance and. coarse W.Knishion. Steam Line Radiation-High alarm and provide for opportunity for a hearing chi,f, licensing Bmnch No..t Division of trip is not considered in any accident after issuance.He Commission expects I.icensing. analysis and therefore raising its that the need to take this actio.n will pa n nanni. m us.4 setpomt does not:(1) Involve a occur very. infrequently. s u ms coom no m -m significant incasse m the probability or A request for a hearing or a petition consequences of an accident previously ' for leave to intervene must be filed with evaluated: or (2) create the possibility of the Secretary of the Commission. U.S. [ Docket No. 50-3871 a new or different kind of accident from Nuc3 ear Regulatory Commission. Washington, D.C. 220B55. Attention: Pennsylvania Power and Ught Co.and any previously evaluated; or (3) involve Anegheny Electric Co-op,inc4 a significant reduction in a margin of Docketing and Service Branch, or maY Consideration of issuance of safety. be dehvered on the Commission s Public DocumentRoom 1717HStreet NW., Arnendment to Facility Operating The Commission is seeking public Ucense and Proposed No Significant comments on this proposed Washington. D.C. by the above date. Hazards Consideration Determination determination. Any comments received Where petitions are_ filed during the last and OpportunNy for Hearing w thin 30 days after the date of ten (10) days.cf thepoticeperiod Jtis publication of this notice will be, requested that.the petitioner promptly so .ne U.S. Nuclear Regulatory. .' considered in making any final ini:rsa the m==iasion by a toll. free.- Commission (the Qpmmission)is determination. De m==i== ion will not e e considering issuance of an amendment riormallymake a Baaldetermination .[ to Facility Operating Ucense No.NPF u unless it receives a request for a ~ '8"' IO 47 .h Western iloion operator should b6'
- 14. Issued to Pennsylvania Power a m.
headng,,t.. < Wye M*" 88,8.".Id'"_Hcad umben ght Company and Allegheny Electric. Comments should be addressed to the U Cooperative. Inc. (the licensees);for v Secretary of the. Commission.U.S. ? i. 3## W - " 8*****8'E* -/ddressed gCoorge W.Knighton operation of theSusquehanna Steam Nuclear Regulatory F- .s
- petitionspeamneand telephone *M.N ElectricStation/UnitflocatedinW ' v.
sWashington D.C.'20555. Atta: Docketing ' = - q- .numbe@latepetition was.mailedglant Luzerne County, Pennsylvania. we -and Service BrancleM f.A:: e . namt Pubucodon dateand page n .ne ame'ndment would raise the Main' By September alk1983, thelicensee tWedamlJtegisestnetice.it - Steam Mne Radja setpointe may file a requiistfor a hearingwith - .@= n h peH also bei. fromless thea or'iquiilto timesur' respect to issuance of the amendment to l
- sent AhstExeontive{tegel Director *' '
normal background 4o e setpoint ofless-the subject facility o' erating license a'nd p 1 U.S. Nuclear Regulatory ranmission... than or eg'ual to seven times normal m - any person whose interest'may be - W:shington, D.C. 20555, and to Philip A. background.in accordance with the' affected by this proceeding and who - Cr:ne. Jr., Esq -Pacific Gas and Electric licensee's application for an amendment wishes to participate as a party in the Company 77JieeleStreet. San dated July 22.1983, and supplemented - proceeding must file a written petition Francisco. California 94106 and Norton.i, by letters dated July 28,1983 and August forleave to intervene. Request for a i , Burke. Betty andFkenciwP.C :Attom, n. ' 2.1983. Previous operations at full hearing and petitions forleave to-- . Bruca Norton. Esq 2002 East Osborn power have resulted in reactor trips and intervene shall be filed in accordance main steam line isolations during normal with the Commission's " Rules of Rxd. Phoenix. Arfiona 85108, attorneya,, plant evolutions.soch as placing a for the licensee.d.s.v.h &. -o 1. Practice forDomestic Ucensing '
- N:ntimely filings ofpetitions for leave -. condensate domineralizerinto service.
Proceedings"in to CFR Part 2.If a Ilefore issuance'of the proposed. N request for a hearing or petition for is intervene. amended petitions;wa. arpplemental petitions and/or aquest6
- license amendment;the Commission '
- leave to intervene is filed by tha above will have made findings required by the' date;the Commission or an Atomic. for hearing will not be' entertained: Om ' Atomic Energy Act of 1954, as amended. Safety and Ucensing Board, designated c.bsent a determination by the7M (the Act) agi the Commission *'s .~ oy the Commission or by the Chairman-Commission, the presiding officer or the' regulations. At:mic Safety and ucensing BoardW'i of the AtomicSafetyandUcensing' . designated to rule on the petition and/or, ' determination that the amendment' *!" ne Conimission has ma Board Pa'nel, will rule'on the request ~ request;that the petitioner has made aA request involves ad significent hazahis" and/or petition and the Secretary or the designated AtomicSafety and Ucensing '. substantial'ehowing of good cause fot" consideration. Under the Commis'sion's ' ' Board willissue a ~ otice of hearing or the granting of a late petition and/or ". tegulations in to CFR 50.02, this means : an appropriate order.' M d % '@ n x . request: hat determinattenWil bir.lW that'opieration of ' tiasedspanabalan Angetthefeetors,.ae$Wdanceivl tyla"M 9:
- 1. As required brio CFR 2.714,'a' '
%w-w v w.m.wCPa*'"MW"g'"'"""g'52#$ on forleave to intervene'shalf se0 .w m. '\\ t
w-
, ~ -, - - -. ,*-,,,,,,,.y---,..--..--..,v- -,,,,.m.v._e -.--e. _ _ _ _., - - - - - -. - - - -., _ - - - -'m m- - ~ - - - - -
e O 's Federal Register / Vol. 48. No. 201 / Monday, October 17, 1983 / Notices 47077 compartments at the time of construction. R-NUCLEAR REGULATORY Regulatory Commission. Washington, DC 20555, Attention: Section Leader, as-as: Has completed the relocation of the COMMISSION emergency escape window handles of the Antitrust and Economic Analysis windows on the Supertiner sleepers. R-AMet ! Docket Nos. 50-424A and 30-425A] Section, Site Analysis Branch. Office of Nuc! Re r Regulatfon. on or Expects to provide low-mounted emergency Georgia Power Company, Oglethorpe b*fOf' lights in any new generation sleeping car Power CegeMMO, Municipal Electric designs. R-aM7: Procedures require that the fcur emergency windows be checked Authority of Georgia, City of Dalton, Dated at Bethesda. Maryland this 7th diy of October 1983. pe-iodically to deter:nine whether they can Georgia; Receipt of Antitrust For the Nuclear Regulatory Ccmmissicn. be readily remcved. R-aM8:Has improved Information escape window exits and has conspicuously Elinor G. Adensam. the visibility of markings on emergency The Georgia Power Company, chief. Licensing smoch m. 4. Dm...sion of marked the outside of the Superliner Oglethorpe Power Corporation, passerger cars to identify the emergency Municipal Electric Authority of Georgia. p Doc. a3-28193 Fded to-im e es em[ window exits. In addition. instructions for the and City of Dalton, Georgia, have snu rso m -u removal of all windows from the outside are submitted antitrust information being placed on the cars at four locations. R-accompanying their application for 83-69:Has designed and is installing fireproof operating licenses for two pressurized het No. 50-2751 containers in the Superliner sleepers and is water nuclear reactors known as Vogtle searching for suitable fireproof trash Electric Generating Plant. Units 1 and 2, "#*"U containers for its other passenger cars. R-a3-located in Burke County, Georgia. The Consideration of issuance of m Believes that its end doors and vestibule data submitted contain antitrust Amendment to Facility Operating doors do not require operating instructions. information for review pursuant to NRC License and Proposed No Significant since they are not unique in design or Regualtory Guide 9.3 necessary t Hazards Consideration Determination operation. R-dJ-71: Will update emergency determine whether there I. ave been any and Opportunity for Hearing procedures and evacuation methods to more sigmficant changes since the completion clearly specify what actions are required of of the antitrust review at the The U.S. Nuclear Regulatory employees in emergency situations, including pictures of key elements of firefighting and construction permit stage. Commission (the Commission)is the evacuation process. R-dJ-72: A refresher On completin of the staff's antitrust consideringissuance of an amendment training program for all employees who work review, the Director of Nuclear Reactor to Facility Operating License No. DPR-on board the train is planned and will Regulation willissue an initial finding as - 76, ssued to Pacific Gas and Electric reinforce material presented in the 1982 to whether there have been "significant Company (the licensee) for operation of Emergency and Evacuation Program and changes" under Section 105c(2) of the the Diablo Canyon Nuclear Power Plant. provide additional points on handling Atomic Energy Act. A copy of this Unit i located in San Luis Obispo' paassengers in emergencies. R-43-7J: Will finding will be published in the Federal California ^' '"[g",## ##,,,j,",f"[#["# Register and will be pent to the The amendment would add a new ed se is ing Washington, DC, and local pubh. rcquirement into the Technical c emergency windows ondopetutingfire document rooms and to those persons Specifications to provide limiting extinguishers that oneincludedin Amtmk's providing comments or information tn conditions for operation should the inlet emergencyprogmm. R-aJ-74:All Amtrek passenger cars built expressly for Amtrak response to this notice. If the intiial ocean water temperature exceed orF met all flammability, smoke emission, and finding concludes that there have not and require surveillence requirements to toxicity guidelines in existence at the time of been any significant changes, request for ensure operability of the ultimate heat construction wherever the then state-of-the-reevaluation may be submitted for a s nk in accordance with the licensee *s art of manufacture was available to meet period of 30 days after the date of the application for amendment dated July 1. those guidelines. R-aJ-75:Has developed and Federal Register notice. The results of is installing briefing t.ards in its Supertiner any reevaluation that is requested will Before issuance of the proposed bedrooms. Is developing briefing cards for the also be published in the Federal Register license amendment, the Commission and copies sent to the Washington, DC, will have made findings required by the balance of the car fleet. Marine-Chevron Shipping Company:Sep. and local public document rooms. Atomic Energy Act of 1954, as amended 16 M-M-97:Has adopted more stringent A copy o[ ge generag ;n{ormation (the Act) and the Commission's standards for flame arresters and replaced all portion of the application for an regugions. those that did not meet those standards. M-6 98:Most existing terminals are incapable operating license and the antitrust The Commission has made a proposed information submitted is available for determination that the amendment of accepting a gangway from the public examination and copying for a request involves no significant hazards accommodations locations. fee at the Commission's Public consideration. Under the Commission's Note.-Single copies of these response Document Room.1717 H Street. NW., letters are available on written request to: Washington, DC 20555, and at the local regulations in 10 CFR 50.92, this means that operation of the facility in Public Inquiries Section. National public document room at the Burke accordance with the proposed es e i f.lu e County Library,4th Street, Waynesboro, amendment would not (1) involve a D 2 pon nt s n me date ofletter, and recommendation number (s) Georgia 30830. significant increase in the probability or Any person who desires additional consequences of an accident prevtously in your request. The photocopies will be information regarding the matter evaluated; or (2) create the possibility of billed at a cost of 20 cents per page ($2 covered by this notice or who wishes to a new or different kind of accident from minimum charge). have his views considered with respect to significant changes related to any accident previously evaluated; or (3) II. Ray Smith. Jr, FedemlRegisterLianon Officer. antitrust matters which have occurred in involve a significant reduction in a the applicants' activities since the margin of safety. construction permit antitrust review The Commission has provided October 12,1981 should subtr.it such requests for guidance for the application of the pomausmra.4 m ss..) information or views to the U.S. Nuclear criteria in 10 CFR 50.92 by providing suasa coca esio-esat
47078 Federal Register / Vol. 48. No. 201/ Mmdiy October 17, 1983 / Notic;s . hy intervention should be permitted However. should circumstarices change examples of amendments that are w considered not likely to involve a with particular reference to the during the notice period such that failure significant hasards consideration (48 FR following factors:(1)He nature of the to act in a timely way would result, for 14a70).One such example is (11) a petitioner's right under the Act to be example. in derating or shutdown of the change that constitutes an additional made a party to the proceeding: (2) the facility, the Commission may issue the limitation restriction or control not nature and extent of the petitioner's license amendment before the presently included in the technical property, financial, or other interest in expiration of the 30-day notice period, specifications.The proposed the proceeding; and (3) the possible provided that its final determination is rmendment is to add an additional effect of any order which may be that the amendment involves no limitation in the event that the ocean entered in the proceeding on the significant hazards consideration. The water inlet temperature exceeds 64*F. petitioner's interest. ne petition should final determination will consider all There presently.is no ocean water inlet also identify the specific aspect (s) of the public and State comments received. timperature limitation in the facility's subject matter of the proceeding as to Should the Commission take this action. Technical Specifications. Inclusion of which petitioner wishes to intervene. It will publish a notice of issuance and the proposed 64*F limitation follows Any person who has filed a petition for provide for opportunity for a hearing. from a reanalysis of component cooling leave to intervene or who has been after issuance. ne Commission expects water performance for heat removal. admitted as a party may amend the that the need to take this action will Based on this consideration and the petition without requesting leave of the occur very infrequently. three criteria given above, we have
- Board up to fifteen (15) days prior to the A request for a hearing'or a petitic.a made a proposed determination that this first prehearing conference scheduled in for leave to intervene must be filed with cmendment requests involves no the proceeding, but such an amended the Secretary of the Commission. U.S.
significant hazards consideration. petition must satisfy th~e specificity Nuclear Regulatory Commission. The Commission is seeking public requirements described above. Washington, D.C. 20555. Attention: c:mments on this proposed Not later than fifteea (15) days prior to Docketing and Service Branch, or may determination. Any comments received the first prehean,ng conference be delivered to the Commission's Public within 30 days after the date of scheduled in the proceeding, a petitioner Document Room.1717 H Street, NW., publication of this notice will be shall file a supplement to the petition to Washington. If.C.by the above date. intervene which must include a list of Where petitions are filed during the last considered in making any final determination. The Commission will not the contentions which are sought to be to (10) days of the notice period, it is normally make a Gnal determination litigated in the matter, and the bases for requested that the petitioner promptly so unless it receives a request for a each contention set forth with inform the Commission by a toll free hearing. reasonable specificity. Contentions shall telephone call to Western Union at (800) Comments should be addressed to the be limited to matters within the scope of 325 6000 (in Missouri (800) 3424700). Seuetary of the Commission, U.S. the amendment under consideration. A The Western Union operator should be Nuclear Regulatory Commission, petitioner who fails to file such a given Datagram identification Number Washington,D.C.20555. ATI'N: supplement which satisfies these 3737 and the following message Docketing and Service Branch. requirements with respect to at least one addressed to Mr. George W. Knighton, By November 18,1983. the licensee contention will not be permitted to {301) 492-7181: date petition was mailed: may file a request for a hearing with participate as a party, ptant name; and publication date and respect to issuance of the amendment to Those permitted to intervene become page number of this Federa R ster the subject facility operating license and parties to the proceeding, subject to any n tice. A copy of the petition should any person whose interest may be limitations in the order granting leave to also be sent to the Executive Legal effected by this proceeding and who intervene, and have the opportunity to wishes to participate as a party in the participate fully in the conduct of the ,st n hington, t 20555. f proceeding must file a written petition hearing. including the opportunity t and to Philip A. Crane, Jr Esq. Pacific for leave to intervene. Request for a present evidence and cross. examine Gas & Electric Company,77 Beale hearing and petitions for leave to witnesses. Street, San Francisco, California 94106 mtervene shall be filed in accordance If a hearing is requested, the and Norton, Burke, Berry & French P.C., with the Commission's " Rules of Commission will make a final Attn: Bruce Norton Esq.,2002 East Practice for Domestic Ucensing determination on the issue of a no Osborn Road. Phoenis, Arizona 85018. Proceedings" in 10 CFR Part 2. If a significant hazards consideration. The attorneys for the licensee. request for a hearing or petition for final determination will serve to decide Nontimely filings of petitions for leave leave to intervene is filed by the above when the hearing is held. to intervene, amended petitions. date, the Commission or an Atomic If the final determination is that the Safety and Ucensing Board, designated amendment request involves no supplemental petitions and/or requests for hearing will not be entertained by the Commission or by the Chairman significant hazards consideration, the absent a determination by the of the Atomic Safety and ucensing Commission rr.ay issue the amendment Board Panel, will rule on the request and make it effective, notwithstanding Commission the presiding officer or the and/or petition and the Secretary or the the request for a hearing. Any hearing Atomic Safety and Ucensing Board designated Atomic Safety and ucensing held would take place after issuance of designated to rule on the petition and/or request, that the petitioner has made a Board will issue a notice of hearing or the amendment. an appropriate order. If the final determination is that the substantial showing of good cause for As required by 10 CFR 2.714, a amendment involves a significant the gr.nting of a late petition and/or petition for leave to intervene shall set hazards consideration, any hearing held request. That determination will be forth with particularly the interest of the would take place before the issuance of based upon a balancing of the factors petitioner in the proceeding and how any amendment, specific in to CFR 2.714(a)(1)(1}-(v) and that interest may be affected by the Normally, the Commission will not 2.714(d). results of the proceeding.The petition issue the amendment until the For further details with respect to this should specifically explain the reasons expiration of the 30 day notice period. action, see the application for
e Federal Register / Vol. 48, No. 201/ M:nd:y, October 17, 1983 / NoticIs 47079 amendment which is available for public abnormal occurrence.The fol'owing which are common to both units. There inspection at the Commission's Public description of the incident also contains is a pair of manually operated steam Document Room,1717 H Street, NW., information on the remedial actions isolated valves in each of the six ste_am Washington, D.C., and at the California planned and taken. lines as shown in Figure 1. These six Polytechnic State University Library, DateandPlace-On April 19,1983, lines are served from steam headers Documents and Maps Departent San Florida Power and Light Company, emanating from the Unit 3 and Unit 4 Luis Obispo, California 93407, licensee for Turkey Point Units 3 and 4, steam generators such that either unit's Dated at Bethesda, Maryland, this tith day reported that the auxiliary feedwater steam generators can supply steam to of October.1983. (AFW) system on Unit 3 had been any or all of the three turbine-driven For the Nuclear Regulatory Commission. Inoperable for five days while the plants pumps. At the time of the event Unit 3 GW W Knishton, was operating at 100% power, Turkey wa., operating at 100% power. Unit 4 point Units 3 an.14 are Westinghouse-was shut down for refueling and steam Chief. Licensing Branch No. J. Division of designed pressurized water reactors generator repair, and the "A" AFW located in Dade County, Florida. pump was out of service for in ooe. swam ria.a wi -sa ees "I Nature andProbable Consequences-modifications. Under these conditions. The AFW system is a safety-related only the isolution valves (3-084A,3-system that supplies the secondary side 084B,3-086A. and 3-086B) from the Unit Abnormal Occurrence; Unavaliability of the steam generators with a source of 3 steam line to the "B" and "C" AFW of the Auxillary Feedwater System feedwater when the mais feedwater pumps were required to be open. system is not in service or only small In addition, during the time of the Section 208 of the Energy feedwater flows are needed.The AFW event, modifications were beirq made Reorganization Act of1974, as amended, system is required to be operable during on the AFW system which consisted of requires the NRC to disseminate plant startup, shutdown, hot standby, adding alternative steam supply lines to information on abnormal occurences and emergency conditions. It is an each AFW pump turbine. A: shor' in (i.e., unscheduled incidents or events engineered safety system and ifit is Figure 1, each alternate line us two which the Commission determines are inoperable, the plant's technical significant from the standpoint of public specifications require that the reactor be. manually-operated steam is alation valves in series. Since the alt?rnate health and safety). The following shut down. system was not yet in operathn, all six Incident was determined to be an At Turkey Point, the AFW system is of the isolation valves (OctA 102A, abnormal occurrence using the criteria shared between Units 3 and 4 (see 001B,002B,001C, and 002C) would published in the Federal Register on Figure 1). Unlike most pressurized water normally be closed. However, ~ February 24,1977 (42 FR 10950). One of reactors, Turkey Point does not have operational testing of the ne.v alternate the general criteria notes that major electrical motor-driven pumps for the steam supply lines required extensive degradation of essential safety.related AFW system. Instead, there are three tagging and manipulation of these equipment can be considered an turbine-driven AFW (A, B, and C), valves. l I I i i l l 1 l l 6
[.h. - Fed;r:I Regist:r / Vol. 48. No. 215 / Friday. November 4. tw1/ Notices ,t 50975 k c30 p.m.-Adjourn. NUCLEAR REGULATORY Power Plant. Unit i located at San Luis COMMISSION Obispo. Cah fornia. f ' November 30.1983 e-330 a m.-NASA Controle and 'gt No. 50-2&SP) (Management The amendment would grant a temporary one. time exception to the Qp $ ( eso p. dance Program issues. facility Technical Specrfications (which Gui 1 m.-Adjourn. Metropoiltan Edison Company, et at prasently require corrective action to - ( ;p. pecember f.1983 No.1); Rescheduling Oral Argument 'O OP"ation within one hour) to permit (Three Mile Island Nuclear Station, Unit reture.at least one reactor coolant loop F.. X Q 330 a.m.-Subcommittee Deliberation. natural circulation tests to be performed October 31.1983. dunng the startup test program with no 1 11 a.m.-Adlourn. Notice is hereby given that in reactor coolant loops in operation in ' 3dard L Daniets. accordance with the Appeal Board's accordance with the licensee's pin.csoc. Monegement Support Office. Ofire order of October 25.1983. oral argument application for amendment dated 8W#"'" previously calendared for December 1. February 10.1983. October 27.1963-1983 has been rescheduled for 9Jo a.m., Before issuance of the proposed Wednesday January 11.1984. in the license amendment. the Commission g ye on. smi ni.4 nw a u "i NRC Public Hearing Room. Fifth Floor. will have made findings required by the I snimo coos rim.es-e l East. West Towers Building. 4J50 East-Atomic Energy Act of 1954. as amended West Highway. Bethesda. Afary/and. (the Act) and the Commission's Dated. October 31.1983. regulalions. paATIONAL SCIENCE FOUNDATION For the APP'8IBoard~ The Commission has made a proposed determination that the amendment Advisory Committee for International Secretary to the Appea/ Board. request involves no significar t hazards consideration. Under the Commission's Programs; Meeting in ox a m ns adu-m u "i regulations in 10 CFR 50 92 this means W"8 CO ' ** ' * [n accordance with the Federal that operation of the facility in . - Advisory Committee Act. Pub. L 92-463. accordance with the proposed the National Science Foundation (Docket Nos. 50-352 OL. 50-353 OL amendment would not (1) involve a e. significant increase in the probability or 4;,.
- announces the following meeting:
Philadelphia Electric Company consequences of an accident previously M MName: Advisory Committee tur (Limerick Generating Station, Units 1 evaluated; or (2) create the possibility of ' L : " blemational Programs, and 2); Oral Argument a new or different kind of accident from Dates: November 21.1983. 8:30 to 11:45 a.m. 'and 1:15 to 5:00 p.m.. November 22.1983. 9M Notice is hereby given that. in any a c en pWoA evaluad w W mv ea 8dcant Muchon in a accordance with the Appeal Board's ac a anal Science Foundation.1800 C "' T Co mission's proposed . Street NW Washington. DC; Room 11a t. g th EE I i Type of Meetmg Open. Inc.. from the Licensing Board's partial determination is based on e, s findings Contact Person: Dr. Bodo Bartocha, initial decision issued on March 8.1983 that the natural circulation test does not Director. Division of fnternational Programs. (LDP-83-11). and its memorandum and ncrease the probability of malfunction National Science Foundation. Washington. order of June 1,1983, will be held at 9:JO of safety.related equipment nor does it DC 20650. Telephone (202) 337-9552. On Thursday. December 15.196J. In the diminish the ability to mitigate the Summary of Minutes: May be obtained NRC Public Hearing Room. Fifth Floor. consequences'of a postulated accident. hoe Contact Person. East. West Towers Building 4350 East
- In addition, the following compensatory l
Purpose of Meeting: To provide advice. West Highway. Bethesda. Afary/ond. conditions will exist dunng the one-time test reimmmendations. and oversight related to Dated October 31.1983. 88Pport for international cooperation in (1) No safety related equipment will edence and engineering. For the Appeal Board. be required to operate outside ofits Agenda: C. lean Shoemaker, normal operating parameters: November 21: Introduction of new Secretary to the Appeo/ Board. (2) The reactor coolant pumps will be m.4 u +4 s es..I ayalf able at all times to return the RCS ts. Reports on NSF reorganization. in ojn.n ,,w to a forced circulation condition; reorganization. neh management plan. f 8tretegic planning for fiacal year 1986. (3) The reactor will be shut down in l Act! ties of the National Science Board. Big ket No. 50-275) ygg, 3 (4) A situation which could lead to an tional act v e7t NSF. Pacific Gas & Electric Co.; acc ent a unct e ent t vember 22: INT Program Report. Report Consideration of issuance of ,p the work of the Office of Management and Amendment to Facility Operating not created by performing the test as the . Future modes of operation of the Licer se and Proposed No Significant
- ]O[* C8 ittee. Summarizing discussions.
Hazards Consideration Determination 9nd n ha b m a one and assignments. Future and Opportunity for Hearing demonstrated at similar plants (North I Anna. Salem and San Onofre): and Y-Deted: November 1* 1983' uc at g atory W M safey Mad Mu@nM d
- @N**,
M^M*'- Commission (the Commienion)is be operable. D
- fC '*ittee Af<magemens Coordinofor.
considering issuance of an amendment The Commission is seeking public r. to Facility Operating License No. DPR-comments on this proposed We n= *meei ma n.s aun..I
- 76. Issued to the Pacific Cas and Electric determination. Any comments received
"'** C0** '555
- w Company (pC&E, the licensee). for within 30 days after the date of operation of the Diablo Canyon Nuclear publication of this notice will be 4.
h. G
e k V. 50W/8 Federal Regislee / wl.' 48. N2 215 / Friday. Nov.mber 4.196a / Notices [' -1 considered in making any final intervene which must include a list of Where petitions are filed during the last d; termination. The Commission will not the contentions which are sought to be ten (to) days of the notice period. it is normally make a fineidetermination litigated in the matter, and the basis for requested that the petitioner prorrotly so unless it receives a request for a each contention set forth with inform the Commission by a toff. free hunns. reasonable specificity. Contentions shall telephone call to Western Umert at (800) j Comments should be addressed to the S !imited to matters within the scope of 325-6000 (in Missouri (800) M2-6;nok Secretary of the Commission. U.S6 the amendment under consideration. A The Western Uman operator should be Nuclear Regulatory Commission, petitioner who fails to file such a given Datagram Identification Number Wr shington. D.C. 2055& ATTN: supplement which satisfies these 3737 and the following message 1 Docketing e'd Services Branch. requirements with respect to at least one addressed to Mr. George W. Knighton. By Dect oet 7.1983,the kcensee may contention wd! not be permitted to Petmoner's name and telephone i fila a request for a hearing with respect participate as a party, number. date petition was maded: plant to issuance of the amendment to the Those permitted to intervene become name: and publication date and page subject facility operating license and parties to the proceeding. subject to any number of this Federal Register notice. any person whose interest inay be limitations in the order granting leave to A copy of the petition should also be i affrcted by this proceeding and who intervene. and have the opportunity to sent to the Executive Legal Director. wishes to participate as a party in the participate fully in the conduct of the U.S. Nuclear Regulatory Cemmission, proceeding must file a wntien petition hearing. including the opportunity to Washington. D C. 20555. and to Phiiip A. for leave to intervene. Request foe a present evidence and cross-examine Crane. [r., Esq.. Pacific Cas & Electric hanng and petitions for leave to witnesses. Company. 77 Beale Street. San ~ inttrvene shall be filed in accordance if a hearing is requested.the Francisco. Cahfornia 94106 and Norton. I with the Commission's " Rules of Commission will make a final Burke. Berry a French P.C.. Attn: Bruce i Prcctice for Domestic Licensing determination on the issue of no Norton. Esq. 2002 East Osborn Road.
- Proceedings" m 10 CFR Part 2. If a significant hazards consideration. The Phoenix. Anzona 85016. attorneys for r: quest for a hearing or petition for final determination will serve to decide the licensee.
3 lesve to intersene is filed by the above when the hearing is held. date, the Commission or an Atomic !! the final determination is that the Nontimely filings of petitions for leave I Safety and Lacensing Board. designated amendment request involves n to intervene. amended petitions. i by the Comrnission or by the Chairman significant hazards consideration. the supplemental petitions and/or requests k of the Atomic Safety and Licensing Commission may issue the arnendment for hearing will not be entertained 2 b b th Boird Panet wifI rufe on the request and make it effective. notwithstanding - Com ss o e presiding of cer or the i and/or petition and the Secretary or the the request for a hearing. Any heanng dzsignated Atomic Safety and Licensing held would take place after issuance of Atomic Safety and Licensing Board i Bocrd wi!! issue a notice of heanng or the amendment. designated to rule on the petition and/or an appropriate order. If the final determm.ation is that the request. that the petitioner has made a As required by 10 CFR 2114. a amendment mvolves a significant substantial showmg of good cause for pttition for leave to intervene shat! set hazards consideration. any hearing held the grantmg of a late petition and/or Th forth with particularity the interest of would take place before the issuance of r'j">'d P b bala 8 m the petitionerin the proceeding and how any amendment. that mterest may be affected by the Normally the Commission will not specified in 10 CFR 2114(a)(1][i]-(s) and results of the proceeding. The petition issue the amendment until the 2J1Ud). should specifically explain the reasons expiratton of the 30-day notice period. For further detai!s with respect to this why mtervent'rm theuld be permitted However, should circumstances change action. see the application for with partren!ar reference to the dunng the notice period such that failure amendment which is available for public followme factors:(1) The nature of the to act in a timely way would result. for inspection at the Commission's Pubhc petitioner's naht under the Act to be example,in derating or shutdown of the Document Room.1717 H Street. NW.. made a party to the proceeding:(2) the facihty. the Comrmssion may issue the Washmgton. D C. and at the Cohfornia nature and ettent of the petitioners license amendment before the Pol) technic State Uruversity L.br.ary, property. fmancial. or other interest in expiration of the 30-day notice period. Documents and Maps Department. San the proceedme: and (M the postible provided that its final determmation is Luis Obispo. Cahforma 9M07. effect of any order which may be that the amendment mvolves no 04 n. eem, da. wryland, this Jts: dav entered m the proceeding on the significant hazards consideration. The of O, aber. tw. petimmer's mterest. The petition should final determination will consider all For tSe Nuc! car Reguiasory Com-mv.m l also identify the specific aspect (s) of the public and State comments received' Cecrx W. Knighton, sub ect matter of the proceeding as to Should the Commission take this action, i g j ty,,,ocvemechs.o I om mer# which petitioner wishes to intervene. it wdl publish a notice of issuance and g,c,,yg Any person who has Ided a petition foe proside for opporturuty for a heanng ,,,,,,, 7.,4 m leave to mtervene or who has been afrer issuance.The Commission expects ? ,,m,,,e,,,,,,,, admitted as a party rnay amend the that the need to take this action wiu 1 p1tition without requestmg leave of the occur very infrequently. I Board up to fifteen (15) days pnor to the A request for a hearma or a Petitio" Regulatory Guide; lesuance, first prehearing conference scheduled ur for leave to intervene must be filed with Availability I tha proceedms.but such an amended the Secretary of the Commrssion. U S. 1 p;tition must satisfy the specificary Nuclear Regulatory Commission. The Nuclear Regulatory Cornmission e. requiremente desenbed above. Washinston, D C. 20655. Attention: has issued a resision to a guide in its Not later than fifleen it5) days prtor to Docketing and Service Branch. or may Regulatory Guide Series. This series has y the first preheatmg conference be dehvered to the Commissioni Public been developed to descnbe and make i si heduled m the proceeshna, a petitionee Document Room.1717 H Street. NW.. asailable to the pubhe methods f shall(de a tupt,'ernent to the peution to Washmston. D.C.. by the above date. acupNble to the NRC staff of ,4 1 1
~ o 26E58 Federal Register / Vol. 49, No.126 / Thursday, luns 28, 1984 / Notices e, IV Direct:r, Divisi:n tf Lictnsing for good if a hearing is ta be h;Id. the cause shown. Commission willissue an Order Accordingly, pursuant to Sections 103' designating the time and place of any 1811,1810 and 182 of the Atomic Energy V such hearing. Act of 1954, as amended, and the The licensee may request a hearing on if a hearing is held concerning this Commission's regulations in 10 CFR this Order within 20 days of the date of Order, the issue to be considered at the Parts 2 and 50,it is hereby ordered, publication of this Order in the Federal hearing shall be whether the licensee effective immediately, that the licensees Register. Any request for a hearing should comply with the requirements set forth inSection IV of this Order. shalb should be addressed to the Director, Implement the specificitems Office of Nuclear Reactor Regulation. This Order is effective upon issuance. described in this ORDER in the manner U.S. Nuclear Regulatory Commission. Dated at Bethesda. Maryland, this 12 day described in NNECo's submittals noted Washington, D.C. 20555. A copy should of lune 1964. In Section 111 herein no later than the also be sent to the Executive Legal For the Nuclear Regulatory Commission. dates in the table. Director at the same address. A request Darrell G. Deenhut. Extensions of time for completing for hearing shall not stay the immediate Dimctor. Division o/ Licensing. Office of these items may be granted by the effectiveness of this. order. NuclearReactorRegulation. MattsToNE UNIT No.1-LICENSEE'S COMMITMENTS oN SUPPLEMENT 1 TO NUREG-0737 Tuo Reesernere ixeness's comsposon actiaMe (or stesse) 9 sessey Parerasser Desday syenem (SPost ta same a se*ery enspres and en swomerunon seen to to Apr s. iss7. NRC Ib. SPoS flay opereuoral and geratore rewme gg, rut scfioMe try Apr. s.1967.
- s. Osmead coneel Room ossen Revise toCRoR) 2t serrue a prograrn plan e vie NRC
. Mw s,1987. 2tt Semt a summary repat to wie NRC mchasng a proposed flavrue scheWe t y Mar. s.1987. ocheme for _ - _ _ 1 Repdesary Gnade 1.s7-Aaner..mg to Emergericy Re-3t Send a report e ete NRC descrteig how vie regeren Composee FetL 29.1964 eponse Facenet mente of $6siplomars 1 to NUREG-0737 have been or ud be mee. 2L 1rrgsament (Ireseesson or worado) remaemente !seme scheNo try.My17,1964. & Uppede Emergency opereeng Proceses (EoPa) et Serr e a Proceanee Genere un Package to rio NRCL Composes May13.1981 4tt psneraere em uppeded EoPe Complete Jurie29.1983. E Emergency Response Fecanee 'It Tecfveces saeport Center supy functor=8 intenm TSC opersecrut** StL operseonel Stegert Center uly neceanal Comspees' 5t Emergency opersects Facefy fuey funceonel Cosmteit' c' eof Bechte enig reene requested tpy NNECo letter dated Aus s isen
- E see ear m=y addeones eine me, be reased se a resust of asser some m ene order.
op-e orm t'T=rmorenry = Eor pencm,g emmenon ce nesseone== Tsc penmerary =$isast PS D== **n*2 N8* *** *=1 (the Act) and the Commission's change will update the listing of ttses cooE rsmew regulations. mechanical and hydraulic snubbers in The Commission has made a proposed two tables of the Technical determination that the amendment Specification and will change the e W27H request involves no significant hazards administrative controls accordingly. c nsideration.Under the Commission's Without such updating, the Consider: tion of lesuanc's of regulations in 10 CFR 50.92, this means identification of snubbers in Tables 3.7-Pacific Gas & Electric Co. that operation of the facility in 3 and 3.7-4 of the Technical Amendment to Facility Operating accordance with the proposed Specifications is no longer accurate and License and Proposed No Significant 8.mendment would not (1) involve a would not,in part reflect the as built Hazards Consideration Determination sigmficant increase in the probability or condition of the plant. and Opportunity for Hearing consequences of an accident previously The Commission has provided The U.S. Nuclear Regulatory evaluated, or (2) create the possibility of guidance in the form of examples about Commission (the Commission)is a new or different kind or accident from the application of three standards set considering issuance of an amendment any accident previously evaluated; or (3) out in 10 CFR 50.92 for determining to Facility Operating License No. DpR-involve a significant reduction in a whether license amendments involve no 76, issued to Pacific Gas and Electric margin of safety, significant hazards considerations (48 Company (the Licensee) for operation of This change will revise the Technical FR 14870). These example are not the Diablo Canyon Nuclear Power Plant. Specifications concerning mechanical applicable to the issue addressed in the Unit 1 located in San Luis Obispo, and hydraulic snubbers to reflect proposed amendment. The basis for California. changes in piping supports that resulted proposing that the proposed amendment The amendment would revise the from the Independent Design does not involve a significant hazards Technical Specification concerning Venfication Program and the Internal consideration is that by assuring that mechanical and hydraulic snubbers in Technical Program which have been the Tables accurately reflect the accordance with the licensee's extensively evaluated by the staff as snubbers at the plant (with attendant application for amendment dated hfarch documented in Supplements 18.19 and change in the administrative controls). 30,1984, 20 to the NRC's Safety Evaluation the previously approved licensing Delore issuance of the proposed Report. These modifications were criteria are met with no effect on any license amendment, the Commission necessary to assure that the affected accident proviously evaluated, any will have made findings required by the systems wete designed to meet the safety related design basis of the facility Atomic Energy Act of 1954, as amended accepted seismic design criteria. This or its operation, or any margin of safety
Federtl luist:r / Vol. 49, No.126 / Thursday, luna 28, 1984 / N:ticis 26659 e Theref;re, th2 three st:ndards ne mit subject m:ttir cf tha proceeding as ta Sh;uld thi Commissi:n tika this cction. because(persti n cf the f:ctlityin which petitioner wish:s to intirvine. It will publish a notice of issuance and accordance with the proposed Any person who has filed a petition for i amendment would not (1) involve a leava to intervene or who has been provide for opportunity for a hearing significant increase in the probability or admitted as a party may amend the after issuance. The Commission expec's i consequences of an accident previously petition without requesting leave of that the need to take this action will evaluated. (2) create the possibility of a Board up to fifteen (15) days prior to the occur very infrequently, new or different kind of accident, or (3) first.prehearing conference scheduled in A request for a hearing or a petition involve a significant reduction in a the proceeding, but such an amended for leave to intervene must be filed with margin of safety. petition must satisfy the specificity the Secretary of the Commission, U.S-The Commission is seeking public requirements described above. Nuclear Regulatory Commission. comments on this proposed Not later than fifteen (15) days prior to Washington, D.C. 20555. Attention: determination. Any comments received the first prehearing conference Docketing and Service Branch, or may within 30 days after the date of scheduled in the proceeding, a petitioner be delivered to the Commission's Public publication of this notice will be shall file a supplement to the petition to Document Room,1717 H Street, N.W., considered in making any final intervene which must include a list of Washington, D.C., by the above date. determination. The Commission will not the contentions which are sought to be Where petitions are filed during the last. normally make a final determination litigated in the n.stter, and the bases for ten (10) days of the notice period, it is unless it receives a request for a each contention se forth with requested that the petitioner promptly so hearing. reasonable specifica.v. Contentions shall infurm the Commission by a toll-free Comments should be addressed to the be limited to matters vithin the scope of Secretary of the Commission, U.S. the amendment underconsidettion. A telephone call to Western Union at (800) Nuclear Regulatory Commission, petitioner who fails to file such a 325-6000 (in Missouri (800) 342-6700). Washington, D.C. 20555, ATTN: supplement which satisfies bese The Western Union operator should be Docketing and Service Branch. requirements with respect to ai least one given Datagram Identification Number By July 30,1984, the licensee may file contention will not be permitted to 3737 and the following message a request for a hearing with respect to participate as a party. addressed to Mr. George W. Knighton. issuance of the amendment to the Those permitted to intervene become (301) 492-7161: date petition was mailed; subject facility operating license and parties to the proceeding subject to any p; ant name, and publication date and any persen whose interest may be limitations in the order granting leave to page number of this Federal Register affected by this proceeding and who intervene, and have the opportunity to n tice. A copy of the petition should wishes to participate as a party in the participate fully in the conduct of the also be sent to the Executive Legal proceeding must file a written petition hearing, and have the opportunity to Director, U.S. Nuclaar Regulatory for leave to intervene. Requests for a present evidence and cross-examine Commission, Washington. D.C. 20555, hearing and petitlens for leave to witnesses. and to Philip A. Crane, Jr., Esq. Pacific intervene shall be illed in accordance If hearing is requested, the Gas & Electric Company,77 Beale with the Commission's " Rules of Commission will make a ffnal Street San Francisco, California 94106 practice for Domestic Licensing determination on the issue of no and Norton, Burke, Berry & French P.C. Proceedings"in to CFR Part 2. If a significant hazards consideration. The Attn: Bruce Norton, Esq.,202 East request for a hearing or petition for final determination will serve to decide Osborn Road, Phoenix, Arizona 85010. leave to intervene is filed by the above when the hearing is held. attorneys for the licensee. date, the Commission or an Atomic If the final determination is that the Safety and Licensing Board, designated amendment request involves no Nontimely filings of petions for leave by the Commission or by the Chairman significant hazards consideration, the to intervene, amended petitions, of the Atomic Safety and Licensing Commission may issue the amendment sunplemental petitions and/or requests Board Panel, will rule on the request and make it effec'.ive, notwithstanding g',e go he ns b et am' ed and/or petition and the Secretary or the the request for a hearing. Any hearing de e lo t designated Atomic Safety and Licensing held woul,d take place after issuance of so the p n ff cer r the Board willissue a notice of hearing or the amer ment. Y d 8 an appropriate order. If the final determination is that the designated to rule on the petit.on and/or As required by 10 CFR 2 714. a amendment involves a significant request, that the petitioner has made a l petitian of leave to intervene shall set hazards consideration, any hearing held substantial showing of good cause for l forth with particularity the interest of would take place before the issuance of the granting of a late petiton and/or the petitioner in the proceeding and how any amepdment. request. That determination will be i 1 that interest may be affected by the Normally, the Commission will not based upon a balancing of the factors results of the proceeding.The petition issue the amendment until the specified in to CFR 2.714(a)(1) (i)-(v) should specifically explain the reasons expiration of the 30-day notice period. and 2.7t4(d). L why intervention should be permitted However, should circumstances change with particular reference to the during the notice period such that failure For further details with respect to this following factors:(1) The nature of the to act in a timely way would result. for action, see the application for petitioner's right under the Act to be example,in derating or shutdown of the amendment which is available for public made a party to the proceeding;(2) the facility, the Commission may issue the inspection at the Commission's Public nature and extent of the petitioner's license amendment before the Document Room,171711 Street NW., property, financial, or other interest in expiration of the 30-day notice period, Washington, D.C., and at the California s j the proceeding; and (3) the possible provided that its final determination is Po;ytechnic Stat niv si Lib effect of any order which may be that the amendmert involves no P P entered in the proceeding on the significant hazards consideration.The Luis Obispo, California 93407, petitioner's interest. The petition should final determination will consider all Dated at liethesda. Maryland this 20th day clso identify the specific aspect (s)of the public and State comments received. of June,1984. f i
t .e i 26660 Federal Register / Vol. 49 No.126 / Thursday, June 28, 1984 / Notices For the Nuclear Regulatory Commission. Specifications, for example a more
- 2. The Manager, Quality Assurance George W. Kaighton, stringent surveillance requirement.
reports to the Executive Vice President. Chief Licensing Bmach Na 3, Division of The proposed amendment,in regard Facilities and Resources Development. Licensing. to the emergency plan. the security plan
- 3. ne position of Manager. Nuclear fra ow. se.inna ru.d w-es. aes aal and their implementing procedures, Projects is deleted, and the Onsite seassa caos rees. sus would require a more stringent Safety Review Group reports to the surveillance program by requiring Technical Assistant to the Vice auditing of the above cited plans and President, Nuclear Power Generation:
(Docket No. 50-2751 procedures once every twelve months Figure 6.2-2 would be revised to instead of the 24 month interval indicate that: Pacific Gas & Electric Co'e, of currently allowed by the Technical 4.The Onsite Safety Revie,w Croup Cor sideration of lasuanc Amendment to Facility Operating Specifications. Moreover, this change is reports to the Technical Assistant to the License and Proposed No Significant required to conform with the Vice President. Nuclear Power Hazards Consideration Determination regulations. i.e.10 CFR 50.54(t) and la Generation. His group previously and Opportunity for Hearing CFR 73.40(d), respectively. Since to CFR reported to the Manager of Nuclear 50.54(t) and 10 CFR 73.40(d) require that Projects. The U.S. Nuclear Regulatory auditing of both the emergency plan and
- 5. A new senior-reactor-operator Commission (the Commission)is security plan and their implementing position called " Senior Operations considering issuance of an amendment procedures be conducted on a twelve Supervisor" is added, reporting to the to Facility Operating I.icense No. DPR-month interval, the licensee by letter Operations Manager.
76, issued to Pacific Gas and Electric dated June 8,1984 requested that
- 6. The " Power Plant Engineer" is now Company (the Licensee) for operation of reference to the frequency of auditing of the " Assistant Plant Manager Technical the Diablo Canyon Nuclear Power Plant, the above plans in the Technical Services," reporting to the Plant Unit 11ocated in San Luis Obispo, Specifications be deleted since they are Manager.
California, required by law.Thus, this change is
- 7. The "Qaality Control Supervisor" is The amendment would revise the also of a type described in example (vii) now the " Quality Control Manager."
Technical Specifications concerning (1) of changes not likely to involve a reporting to the Plant Manager. frequency of auditing the emergency significant hazards consideration (48 FR
- 8. The " Technical Assistant to the plan and the security plan and 14870). Accordingly. based on these Plant Manager" is now the "Ase6stant associated implementing procedures, (2) considerations and the three criteria Plant Manager Support Services".
limits of working hours for unit staff, (3) given above, we have made a proposed
- 9. A new position called " Personnel prompt notification of failure of determination that this portion of the and General Services Manager"is f
pressurizer power operated relief valves amendment request involves no added (PORVs) or pressurizer safety valves,
- significant hazards consideration. We and (4) arfministrative controls in also conclude that deletion of the
- 10. The titles of various supervisors accordance with the licensee's reference to the frequency of auditing in have,been upgraded to " Manager".
applications for amendment dated the above areas in the Technical Section 6.2.3.4,"Onsite Safety Review December 17.1982, January 11.1963, Specifications is acceptable. Group (OSRC), Authority", would be revised to show that: January 11. June 6, and June 8,1984. In regard to the requested amendment Before issuance of the proposed on working hours and the requirement t
- 11. The OSRG reports to the Technical license amendment, the Commission notif the Commission within 24 hours Assistant to the Vice President. Nuclear will have made findings required by the of a allure of a PORV or a pressurizer Power Generation:it previously Atomic Energy Act of 1954, as amended safety valve and submit a written report reported to Manager, Nuclear Projects.
(the Act) and the Commission's withi14 days of the occurrence, these Section 6'5.1.2," Plant Staff Review , regulations. are representative of changes shown in Committee (PSRC). Completion" would The Commission has made a proposed example (ii) above. 'That is, the addition be revised to indicate that: determination that the amendment of these changes imposes more stringent
- 12. The members titles agree with request involves no significant hazards controls on the number of hours an their new titles in Figm 6.24 consideration. Under the Commission's individualis permitted to work and the
- 13. The l&C Maintenance Manager regulations in 10 CFR 50.92, this means new requirement to notify the and the Engineering Manager have been that operation of the facilityin Commission within 24 hours and submit added to the Committee.
accordance with the proposed a written report within 14 days after the Section 6.5.2," General Office Nuclear amendment would not (1) involve a occurrence of a failure of a PORV or Power Plant Review and Audit-significant increase in the probability or pressurizer safety valve. Based on these Committee (GONPRAC)", would be consequences of an accident previously considerations and the three criteria revised to indicate thst: evaluated; or (2) create the possibility of given above, we have made a proposed
- 14. In Section 6.5.2.2. " Composition",
a new or different kind of accident from determination that this portion of the the title " Manager, Nuclear Projects" is any accident previously evaluated; or (3) amendment request involves no replaced with " Project Manager, Diablo involve a significant reduction in a significant hazards consideration. Canyon". margin of safety. With regard to administrative
- 15. In Sections 6.5.2.9, " Authority",
The Commission has provided controls, the proposed amendment and 6.5.10. " RECORDS *, the title " Senior guidance for the application of these would revise Figure 6.2-1 to indicate Vice President, Feellities Development" criteria by providing examples that are that: is replaced with " Executive Vice considered not likely to invnive a
- 1. The Senior Vice President. Facilities President, Facilities and Electric significant hazards consideration (48 FR Development is now the " Executive Resources Development"(see also 14870). One such example is (ii) e Vice Pre:Ident, Facilities and Electric change 1).
change that constitutes an additional Resources Development", reporting to The new title of" Executive Vice limitation, restriction, or control not the Chairman of the Board and Chief President. Facilities and Electric. presently included in the Technical Executive Officer. Resources Development" and the new
t 26660 Federal Rtgiste../ Vol. 49. No.126 / Thursday. June 28,19% / Notices i for the Eclear Regulatory Commission. Specifications. for example a more 2.The Manager. Quality Assurance George W. Kalghton. stringent surveillance requirement. reports to the Executive Vice President. Chief.Ucansig Rmnch #si.t Divis4aa of ne proposed amendment,la regard Facilities and ResourceeDevelopment. to the emergency plan, the sacarity plan-3.%e position.of Manager Nuclest Lic*a81% m,,.u.a +..[. and theirimplementing procedums, Prefects is deleted, erid the Oristte trs o egime ru.as oes Safety R~eview Crottl reportd to the' ' i
==== come rees ws;,',.' would requhe a more stringente i surveillance prograntby requiring Technical Assistantto'theVice' auditing of theabove cited plans and President, Nuclear Posec Generation" I et ses.so-27slpv n : m - procedume oncesarytwelve esenths - Figure's.2-2 souldbe revised to * ,cfgfQ7QQ instead of the 24 month latervat 4.The OnstriSs.... i Indicate that:, Consideration of lasuanceAf currently allowed by the Technical fityReview Group Spec 1Ecanons. Moreover; this change is reports to the TechnicarAssistant to the ] Amendment to Facility Operating required to conform with the '~ '" Vice President. Nuclear Power Ucense andProposed No Sign"'unt regulations, i.e.10 CFR 50.54(t) 'and to, Generation..%!s group previousTy Hazards Consideration Determ.._stion CFR 73.40(d). respectively. Since 10 CFR reported to the Manager.of Nuclear and Opportunity for Hearing 50.54(t) and 10 CFR 73.40(d) require that - Projects. ~ ". He U.S. Nuclear Regulatory auditingof both the emergency plan and
- 5. A new sentor-reactor-operator Commission (the Commission)is security plan and their implementing position called " Senior Operation =
considering issuance of an amendment procretures be conducted on a twelve Supervisor is added, reporting to the to Facility Operating Ucense No. DpR-month interval, the licensee by letter Operations Manager. 76, issued to Pacific Gas and Electric. dated June & 1984 requested that
- 6. He " Power Plant Engineer" is now Company (the IJcensee) for opera tion of reference to the frequency of auditing of the " Ass [stant Plant Manager, Technical the Diablo CanyonNuclear Power Plant, the above plans in the Technical Services." reporting to the Plant Unit f located in SanLuis Obispo, Specifications be deleted since theyare Manager.
California. required by law.nus, this change is
- 7. The "Qualily Control Supervisor" is ne amendment would revise the also ol a type described in example (vil) now the " Quality ControlManager,"
Technical Specifica tions concenung (1) of changes not likely to involve a reportingin the Plant Manager. frequencyof auditing.the emergency significant hazards consideratforr (48 FR
- 8. He " Technical Assistant to the plan and the security plan and.
14870). Acennlingly, based on these Plant Manager"is now the " Assistant associated fmpfementing procedures. [2] considerations and the three criteria Plant Manager. Support Services"., limits of working hours for unit staff,(3) given abomwe have made a proposed
- 9. A new position called," Personnel prompt notification offaifun of-determination that this portion of the 9 pressunter poweroperated refiefvalves amendment request involves no andGenera1ServicesManageg"is (PORVsf or pressuriser safety valves, sign 16 cant hazards considers tion. We
- dded. $ titlabbou[s'u.p rviNro '
- 10. n and (4) avf rmhtrative controls in.
. also conclude that deletion of the-hava6been upgraded to "Manaaer". accordancewiththelicenhee's ' reference to the frequency'of auditingin Section 61L4."Onatta SafetyReview applications for amendment dated the above areasin the Technical ' " ' Group (OSRG). Authority" would be December 17.1982, January 11 1983, Specifications is acceptable. ' ' revised to show thsW * *'m January 11 June 6 and June 8,1964. . In regard to the requested amendment 11.%e OSRG rep 4 rte to the Tedmical BeforeIsauance of the proposed. 3 on working hours and the requirement t " Asalatant to the Vice Prealdent Nnclear license amendment.the Commission.- notify the Commission within 24 hours < PowerGeneratiorcitpreviously. will have made. findings'requf:ed by the of a failurs of a PORVora pressurizer. mported to Manage.mcledroks-Atomic Energy Act of,1954, as amended, safety valve and submit a written report Secdon6A1.2, MaatMMew (the Act) and the Commisston's, ' withi 14 days of the occurrence; these Committee [PSRC). Completion", would 3 ~ ~" regulations." are representative of changes shown in be mvised to indicate dise ne Commission has m'ade e proposed example (ii) above. net is, the addition 11 The mernben tides agne widi determination that the amendment of these changes imposes more stringent request involves no significant hazards controls on the number of hours an their new tideain Mgum m 13.The l&C Maintenance Manager consideration. Under the Commission's individualis permitted to work and the regulations in 10 CFR 50.92, this means new requirement to notify the and the Engineering Manager have been thatoperationof the faci!!tyin Commission within 24 hours and submit added to the Committee. accordance with the proposed a written report within 14 days after the Section a.5.2," General Of6ce Noclear amendment would not(1) involve a occurrence of a failure of a PORVor Power Plant Review and Audit significant increase in the probability or - pressurizer safety valve. Based on these Committee (CONPRAC)". would be consequences of an accident previously considerations and the three criteda - revised to indicate that,
- evaluated; or (2) create tlie possibility of given above, we have made a proposed
- 14. In Section 8112. " Composition",
a new or different kind of accident from determination that this portion of the the titia
- Manager, Nuclear Projects"is any accident previously evaluated or (2) amendment request irrvolves no replaced with " Project Manager, Diablo invoive a significant reduction in a significant hazards consideration.
Canyon,. With regard to administrative
- 15. In Sections 6.5.19," Authority'*,
margin of safety. '. 6 provided controls, the proposed amendment and 6110
- RECORDS". the tide " Senior na Commisslon h guidance for the ap' plication of these would revise Figure 0.5-1 to indictte Vice President, Facilities Development" is replaced with
- Executive Vice criterts by providing exertples that are that:
a l considered not hkely to involve a 1..%e Senior Vice President. Facilitteo President, Pacilities and Electdc significant hazards consideration (48 FR Development is now the " Executive - Resounes Development *(see also 1440). One such exaraple is (li) e Vice President, Facilldes and Electric change 1). change that constitutes an' additional Resources Development", reporting to The new title of" Executive View limitation. restriction, or control not the Chairman of the Board and Chief President. Faci!! ties and Efectrfe. t Resources Development", and the new ( presently includedin the Technical Executive Offloer. - t l l
M t [ O 1 ...v' i Federal Register IVd) 49(cNo426 /Prhursti@ Inrie'.287'1969)llN otft d N 1 __36sii s q p, w .;15);ais Not
- g. ',
N sMped -' Nn, cons ManagerEC detinnin'dt! - 'md interveneshfclipstiertnrht,a list 6f/ttc fugtheestendtlieHtfilriW . meninftment to u'elitfa ~ noimally make a fhialdetejsdiati the contentions 4thiclgiare sonsht torbort i esa it received ~af r'Qini gt for d litigated in.the mattergnd the bases'fori e i ' % Diabitz Canypn y'fnereasJindependence% tlie Q4fGnctio VN< ; hearing.*W4 7W4W,'Cemfn'ents'sho fosch cpatenliga s'et forth withs!W[all - ~ re'asonable 'speilficity, Contentionai si He deletion'of references to the' . Secretary of the Commission U.S.? " "belimited to matters.within.the scope of s Manager, NuclearProjects (changes 3,4,5 - Nuclear Regulatory Commission $t'W"g $.the' amendmen 11 and 14)'was made neceuary when t'I Washington lD.C 20555. Attn;DoclieYn .~ petitioner wh'o' fails W supplement which sa(d. file such ajn ; the Manager of Nuclear Projects' '.' and Servfce Bran ~ch. ' > ' N*": tisfies these e, By July 30.1984, the liceiis# ' * $aTfile T. requirements With respect to at least one position 'was iricorporated into the-ee c l overall PG&E/Bechtel ProjectM. a request for a'lis with respegt,opM participata as.a partympb,ed to.l. s contentionwu1.notbe,permitt Organization and no longer existed as a
- issuance of the~ amin int to the v.
separate entity. In the GONPRAC ~ *
- subject facility operating license andy.*(IM%os,[e Pernpitted to ldie organization, the change from **Ma'n'ager, e
h Nuclear Projects"to 'P, Diablo Canyon'*,has." Project Manager,' limitations,in the order granting leave to affected b wishes to'y this proceeding and who'08, intervene, and have the_ no effect on' participate as a party,in the operations. since the individual involved proceeding must file's written petition'O, particlyate fu,llyinthe conduct of t!;e' ', d and his responsibilities are the same'.T. for leave to intervene. Requests for a-nearingj liiBudingK6pportsnity to ' ] ~ ', %e new Senior Operations ' ', hearing'and petitions for leave to s present evi ~co' sad ~ xamtnd -- Supervisor (change,5)will so;fplenisiitg'inferveri,e'aballbsflI.ed th"accordah G E. witne M.4 theFOpnettons hfanagefin'hisdutfeT with.thigConihils'dlon's ydisfoU 1"1 Ifath HelilFnb[ asia'nis~any authoff
- Practicef6(DonssifELiceitsing*@G Gdetermihatibiodthe(ts'saeo
.cnEmWf i',f16ht N-ons Mane or hfa+ Procee s"in to CFR Put 2.1 {g;.. '= ~ "Is# ' ~ti significant&hhnfsfaeisti ' MA f.F 1 ' ~b , finalyelerminatfonkillseivet#dlNidh.. org . %be f6 Co" (bii'bf ad Atomid- 'when thehearingisheldMN.ofaw g ' thd pe'riltkandwilf
- If the final determination ~is that thM.
7espoits(to9per' t6t'jj Safety an'd Licensidg Board l desigMd"* clos ' ' - 1 by~ the Co'mmissidhd by the Chairman % amendment requestinvolves no msm a provi a questi blerps.WMM9 of thi Ato Safetta'nd Ucensing 7f ' Commission may.lasue the ame significant hazardsLconsideration, the r Thereina infchahges'laOnrr9M BoardPane Yule on the rejuesk:' ? f l organizatioiQchariges'6 thro 6gh 9112 dnd/or petiti iihd th'e $ecietary of thk' the request for a,ctlye, notwithsta and make it affe and 13)~ area necessary,because of the j designate'd Aldhilh Safety and Licensing" hearing. Any hearing; significantincrpse in plant staff over" Board willissie's ri6tice of hearing or: held would take) lace afte'r issuance of i the last three years and the'additioiiof' an appropriate order.' - the amendment., ~ several new functions and work
- groups As required by to CFR 2.714. a If the final determination is that the.
r i at the plant. At the'same time, the petition for leave to intervene shall sef amendment involves a significant i ! changes simplify and streamline the forth with particularity the interest of hazards consideration, any hearing held reporting relationships, promoting safety the petitioner in the proceeding and how would take place before the issuance of i and efficiency of operation. that interest may be affected by the any amendment. The Commission has provided results of the proceeding.The petition Normally, the Commission will not guidance in the form of examples about should specifically explain the reasons issue the amendment until the the application of three standards set why intervention should be permitted expiration of the 30-day notice period. out to CFR 50.92 for determining with particular reference to the liowever, should circumstances change whether license amendments involve no following factors:(1)The Nature,of the during the notice period such that failure sigmficant hazards considerations (48 petitioner's right under the Act to be to act in a timely way would result for FR 14870). These examples are not made a party to the proceeding:(2) the example,in derating or shutdown of th4 applicable to the issues addressed in nature and extent of the petitioner's facility, the Commission may lasue the this poition of the proposed amendment. property, financial, or other interest in license amendment before the The basis for proposing that the the proceeding: and (3) the possible expiration of the 30 day notice period, p proposed amendment does not involve a effect of any order which may be provided that its final determination is significant hazards consideration is that entered in the proceeding on the that the amendment involves no the administrative controls change, petitioner's interest. The petition should significant hazards consideration. The which relate solely to organizational ~ also identify the specific aspect (s) of the final determination willconsider all. G ( structure,do not have anydirect bearing subject matter of the proceeding as to' public and State comments received.M h on the operation of.the facility and .m. which petitioner wishes to interven's. Should the Commission take this action, p would not (1) Involve a significant Any person who h*as filed a petition for it will pub!!sh a notice ofissuance and t increase in the probability or. ~ leave taintervene or who has been* provide for opportunity for a heari'ng s ,l4 consequences of an accident previously admitted as a party may amend the.. after issuance. The Commission expects evaluated. (2) create the possibility of a petition without requesting leave ~ of the that the need to take this action'will. new or different kind of accident, or (3) floard un to fifteen (15) days prior to the. occur very infrequently. ~ involve a significant reductin in a-first pro scaring conference scheduled in A request for a hearing or a petition ' margin of safety. the proceeding. but such an amended for leave to intervene must be filed with / 1
j .~ ^ 26662 Federal R e / Vol 49 Ns.126 / Thursday, Jun2 28,1984 / Notices s the Seemiary of the t'a==lseien, U.Sv [ Docket No,56 3441 III Nuclear Regulatory Co==Wog. Rochester. Gem & Electric Casp.plL. RC&E responded to6Ceneric IAtter S&= I WashiamD6Cassam Attentiesc 33 by lettetdated April.15,less.By #,. 9. Ginne Nuclear Power flert% Order.%'en letters dated August 3.1983 Novem Docketing'an4ServiseM.$ Confirmine UcenseaComadtmenta k de M W w g,N,,,,,,,gof Dar ===aReem N M N W ~ f, y y . Wa=hington5.11C.by therahsordmenp: F W.e h negotfations with tha NRC ataff. In these Whera petitione ere hd dering the lmes' RocIEstEbnaNiElect'ric' submittals RG&Emade commitmants to ten (1@ daye d thenonce peWla S Corporation (EG&E)(thelicenhtheg complete the basicrequhamanta- %e requeated tAatthe yedWonerpromptlyte. holder of Provisional Opersung Mcease followingTable nummarizing RG&E's inform the Comedesion by a toII-fkee 6 - No. DPR-18 which authoriano the schedular commitmentswor status wast telephone call to Western Union at (800} operation of the R.E.Cinna Nuclear developed by the NRC staf fbesa b 3250000(in Woouri(80@ mh Power Plant (the facility) at steady-stata Generic Letter and the information i The Western Union operator should be power levels not in excess of1520 provided by RGaE' given Datagram Identification Number megawatta thermal.no facility is a RG&E's commitments include (1) 4't 3737 and the following message pressurized water reactor (PWR) located dates for providing required subadttala addressed to Mr. George W. Knighton. In Wayne County, New York. to the NRC,(2) dates forimnH W (301) 492-7161: date petition was mailad; certain requirements, and (3) a schedule, pfant name, and publication date and II for providing implementation dates for page number of this Federal Register Following the accident at %ree Mile other aquirements.%ese latter notice. A copy of the petition should Island Unit No. 2 (TMI-2) on March 28, implementation dates will be reviewed, also be sent to the Executive Legal tro, the Nuclear Regulatory negotiated and ennfirmed by a Director, U.S. Nuclear Regulatory Commission (NRC) staff developeda subsequent order. Commission. Washington, D.C. 20555, number of proposed requirements to be The NRC staff reviewed RC&E's April and to Philip A. Crane, Jr., Esq. Pacihc implemented on operating reactors and 15,1983 letter and entered into Gas & Electric Company,77 Beale. on planta under construction.These negotfallona with the licenses regarding Street. San Francisco, California 9410s requirements include Operational schedules for meeting the Y -- -" and Norton, Burke. Berry & French 0.C, Safety, Siting and Dealga, and. ofSupplement1toNUREGW37 Asa Attn: Bruce Norton, Esq.202 East Emergency Preparedness and are result of thesanaqotiations, the kranmaa Osborn Roed Phoenix, Arizona 8501a, intended toprovidesubstantial. modified cortain es' tes by lettere dated attorneys for thelicenses. additional protection in the operation af-August 3,1983 November 28,1983, April e and SMMMOta5fladsthate Nanthnaly fihngs of petidons m 1asee nuclear facilities and significant,, i.c, f ponse tha lo' r moedk" d to int arnended peuttons, -i, gg , h! Is da 8upP Pendes and/or mrues$ Commisalam: requirements.De NRC.. the acr* fan' al.DU-2 and the africist '.'. for hearing will net be entertained 'l.. edies andinv@im &. 2 ' staff. concludes thatthe adiedule Wb$ AtemkSWandI,feenetngBomff y'D Action Nn Requirements,"andlag' ' , emergencydesponse,~P%.W. orth In 37 designated to nie on the petitfotz andfor-request! thattlie petitionerhes made s' - Supplement 1ste NUREG wa7.,?* #,' Inaria'w.althe foregoing thava L,. "Requireinanta for; Emergency n determramf tina 4the t= tioned ',, * ~ substanffWebowing of goatf tause foD 'Capabi!!!y "Among.thaea asquisodienta[,,3 RGAKs comuniemaata ara terguired la the tlie greeting bf E Tatti petitfon sad /or are a number ofitems canaiating et interestof the public baalth and safety l I request.*I1:st determination wilf be ~ emergencyressiones facility operahih*ty, and abould, therefore, beconfirmed by based upon a balancing of the factors emergency procedure implementation, an immediately affective Order. specifled in to CFR 2.714(a)D)(I)-{vl addition ofinstrmnantation, possibis gy, n ;5 r and 2.714(dJ., control room design mnitmemera== and For further details with respectta'thla ; specific Information to be submuta,1 Accordingly. pursuant to Sections 103, action, neef the applicattna for, C,- On December 17,. lee 2.a lettaa,,, tail tetoand181af the AtomicEasesy amendment imbich is avaliable for peblia..,a (GenericLetter 8843} was sent to.all Act ofISE,aa'=an'lael and the Commiselon's segulationsin le CFR ' inspection at the,Comssission's Pebije, licananes of operating reactore, 'a'ad Parts 2 and8th itlahereby oedered, Doenanent Roosa 1717 H Stree6MW, applicants for opereting licensee, Weshington$ D.C.,;and et the California. holders of construstian persiste e!!ecuvaimmediately,that thalicensee ,. r Polytechnis Stees Univers6ty Ubsery;. enclosing Supplement i to NUREG W37. shall: DoenmentsandMape Dippersemot, Ben, In this ledet opersilas peactog licanesee , implement ahmapesias Itume dunesend h6 O' '!,uis Obispo.faliforniaaMor. < *..., and holders.of construcdes permits.. RGaE's sahanteiseetsd ie sesuma ID hassim - tide OADepttadie mammmedunsthod he - were requested fo lurnich the following , 's..me r. r+r ' 1 d. Detad at Bethsees.ndssytead,tids soih day. Informatian, pursuant to to CER SIL84(f), no later than the delas 19 she,Tahien of June, test.,n e m, r,s . M o.n. 3.! w. no lalar them April,1A,1983:,. n,,;,9,. -Extenedeneof theforcompfeWng - , u,., L,,,g s,. 2 (1) A psoposed schedule fee :.,9 AU
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%y y Feder:1 negister / Vol. 48, No.110 / Tu sday, jun / 1983 / Noticis 26383 adversely affect the state of emergency Technical Specifications (which intervene shall be filed irt accordance preparedness at Nine Mile Point. We presently require immediate corrective with the Commission's " Rules of conclude, therefore, that the licensee's action to return at least one reactor Practice for Domestic 1.icensing request for an additional exemption coolant loop to operation) to permit Proceedings ** in 10 CFR Part 2. If a should be granted. natural circulation tests to be performed request for a hearing or petition for during the startup test program with no leave to inter ene is filed by the above III reactor coolant loops in operation in date, the Commission or an Atomic Accordingly, the Commission has accordance with the licensees
- Safety and Licensing Board, designated determined that, pursuant to 10 CFR application for amendment dated by the Commission or by the Chairman 50.12 the exemption requested by the January 8,1983.
of the Atomic Safety and Licensing licensee's letters of August 20 and Before issuance of the proposed Board Panel, will rule on the request October 6,1982, as revised by letter license amendment. the Commission and/or petition and the Secretary of the dated March 9.1983. as discussed will have made findings required by the designated Atomic Safety and Licensing above, is authorized by law and will not Atomic Energy Act of 1954. as amendei Board willissue a notice of hearing or endanger life or property or the common (the Act) and the Commission's an appropriate order. defense and security, and is otherwise regulations. In the public interest.The revised The Commission has made a proposed As required by 10 CFR I 2.714 a exemption is hereby granted as follows: determination that the amendment petition for leave to intervene shall set in order to allow for offsite agencies' request involves no significant hazards f rth with particularly the interest of the schedular constraints, the next consideration. Under the Commission's petitioner in the proceeding, and how emergency preparedness exercise at the regulations in 10 CFR 50.92, this means that interest may be affected by the Nine Mile Point Nuclear Station. Unit that operation of the facility in results of the proceeding. The petition No.1 shall be conducted during the accordance with the proposed should specifically explain the reasons week of Septerr.ber 28,1983. This amendment would not (1) involve a why int rvention should be permitted exercise shallinclude appropriate significant increase in the probability or with particular reference to the participation by the State and local consequences of an accident previously following factors:(1) the nature of the authorities. evaluated; or (2) create the possibility or petitioner's right under the Act to be The NRC staff has determined that the a new or different kind of accident from made a party to the proceeding: (2) the granting of this additional Exemption any accident previously evaluated; or (3) nature and extent of the petitioner's will not result in any significant involve a significant reduction in a property, financial, or other interest in environmentalimpact and that pursuant margin of safety. the proceeding: and (3) the possible to to CFR 51.5(d)(4) an environmental The Commission's proposed effect of any order which may be impact statement or negative determination is based on its finding entered in the proceeding on the declaration and environmental im;.act that the natural circulation tests will be petitioner's interest. ne petition should appraisal need not be prepared in conducted using operating procedures also identify the specific aspect (s) of the connection with this action. that provide compensatory measures subject matter of the proceeding as to that maintain a commensurate level of which petitioner wishes to intervene. D ed Bethesda, Maryland this 27th day safety as the Technical Specifications Any person who has filed a petidon for 4 Y that the proposed amendment would leave to intervene or who has been For the Nuclear Itegulatory Commission. temporarily relax. Such compensatory admitted as a party may amend the Itobert A. Purple, measures include termination of the test petition without requesting leave of the Deputy Director, Diris/on off.icensing. Office and restoration of at least one reactor Board up to fifteen (15) days prior to the o/ Nuclear /teactorRegulation. coolant loop to operation in the event of first prehearing conference scheduled in gra o.a spaess ru. man aos a=1 . abnormal system parameters. the proceeding, but such an amended 7 coot rieseus %e Commission is seeking public petition must satisfy the specificity comments on this proposed requirements described above. l[ g g g g. determination. Any comments received Not later than fifteen (15) days prior to within 30 days after the date of the first prehearing conference Southern Cailfornia Edison Co., et al.; publication of this notice will be scheduled in the proceeding, a petitioner ConsideraUon of leauance of considered in making any final shall file a supplement to the peution to determmation. The Commission will not Amendment to FacNity Operating License and Propoeod no Significant n rmslly make a final determination - intervene which must include a list of Hazards Considwation DetwminaHe unless it receives a request for a the contentions which are sought to be litigated in the rnatter, and the bases for 8 PpwtunW h HeaMg hp,grnents should be addressed to the each contention set forth with %e U.S. Nuclear Regulatory Secretary of the Commission, U.S. reasonable specificity, Contentions shall Commission (the Commission)is Nuclear Regulatory Commission, be limited to matters within the scope of considering issuance of an amendment Washington, D.C. 20M5, ATrN: the amendment under consideration. A to Facility Operating I.icense No. NPF-Docketing and Servt< e Branch. petiuoner who falls to file such a 10, issued to Southern California Edison Dy July 7,19s3, ths licensees may file supplement which satisflee these Company, San Diego Cas & Electric a request for a hea ing with respect to requirements with respect to at least one Company, the City of Riverside, issuance of the amendment to the contention will not be permitted to Cahfornia and the City of Anaheim. subject facility operating license and participate as a party. California (the licensees), for operation any persons whose interest may be %ose permitted to intervene become of the San Onofre Nuclear Generating affected by this proceeding and who parties to the proceeding. subject to any Station Unit 2 located in San Diego wishes
- to participate as a party in the limitations ln the order granting leave to County, California.
proceeding must file a written petition Intervene, and have the opportunity to The amendment would grant for leave to intervene. Request for a participate fully in the conduct of the temporary exceptions to the facility hearing and petitions for leave to hearing, including the opportunity to
[ 26384 Federal Regist Vol. 48, No.110 / Tursd;y. Juns 7,1983,.votices present evidence and cross-examine R. Kocher. Esq., Southern California _ recent large increase in the number of Edison Company,2244 Walnut Grove local Covernmer.t units undertaking witnesses. Avenue, P.O. Box 800, Rosemead. single audits and thereby needing to If a hearing is requested. the Commission will make a final California 91770 and Orrick, Herrington establish contact with a cognizant determination on the issue of no & Sutcliffe, Attn.: David R. Pigott. Esq agency, necessitates a dissemination of significant hazards consideration. ne 600 Montgomery Street, San Francisco, the methodology to a wider audie nce. final determination will serve to decide California 94111, attorneys for the The purpose of this notice is to help when the hearing is held.. licensees. local governments and other localities If the final detennination is that the Nontimely filings of petitions forleave that have not been assigned a Federal amendment request involves no to intervene, amended petitions, significant hazards consideration. the supplemental petitions and/or requests cognizant agency identify the Federal Commission may issue the amendment for hearing will not be entertained cognizant agency that will be and make it effective. notwithstanding absent a determination by the responsible for administering the single ""dit* the request for a hearing. Any hearing Commission the presiding officer or the held would take place afterissuance of Atomic Safety and Licensing Board Cities, counties and towns that have the amendment. designated to rule on the petition and/or not been notified of a cognizant agency If the final detennination is that the request, that the petitioner has made a assignment are assigned to the amendnent involves a significant substantial showing of good cause for department or agency that is responsible hazards consideration any hearing held the granting of a late petition and/or for negotiating their indirect cost rates would take place before the issuance of request. That determination will be under Circular A-87. " Cost principles for any amendment. based upon a balancing of the factors grants to State and local governments." Normally, the Commission will not specified in 10 CFR 2.714(a)(1)(iHv) and if one has been assigned, as listed in the issue the arnendment until the 2.714(d]. February 28,1980 Federal Register expiration of the 30-day notice period. For further details with respect to this (pages 13396-13408). Cities, counties and Ifowever, should circumstances change action, see the application for towns not assigned a Federal agency during the notice period such that failure amendment and the licensees' submittal dire'ctly or under Circular A-87 are to act in a timely way would result, for of April 15,1982, which are available for assigned to the Federal agency that example, in derating or shutdown of the public inspection at the Commission's provides the greatest amount of grant facility, the Commission may issue the Public Document Room,171711 Street, funds. license amendment before the N.W., Washington D.C., and at the San School districts ' are assigned to the expiration of the 30-day notice period. Clemente Library 242 Avenida Del Mar. Department of Education, except for provided that its final determination is San Clemente. California. those in Arkansas. Georgia, Maryland. that the amendment involves no significant hazards consideration. The Dated at Bethesda Maryland, this stet day Minnesota. Oregon, Utah, and Puerto of May. isas. Rico. School districts to those States and final determination will consider all For the Nuclear Regulatory Commission. Puerto Rico are assigned to the S d tha e th a action. N It willpablish a notice ofissuance and Chief, ucensing smnch No. 3, D/r/sion of Special purpose districts are assigned provide for opportunity for a hearing sing; as foHows after issuance. He Commission expects W"*'"'**'""*"t Housing Agencies-Dept of Housing & that the need to take this action will Urban Development occur very infrequently. - - - Transit Agencies-Dept of be be w th D*"' # 8" " for eave te n BUDGET Planning a Development Districto-Dept the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Federal Agencies Responeltale for
- C' Washington, D.C. 20555. Attention:
Administering Ludits of Local AlrPort Authorities-Dept of Docketing and Service Dranch, or mry be dehvered to the Commission's Public Governments and Special Purpose Transportation Districts Document Room.171711 Street. N.W., Port Authorities-Dept of I Washington, D.C. by the above date. AGesecv: Office of Management and Transportation l Where petitions are filed durir g the last Dudget. Sewer & Water Districts-ten (10) days of the notice period, it is Acisose: Notice. Environmental Protection Agency requested that the petitioner promptly so Last year Director Stockman wrote to All Other-Agency providing most grant inform the Commisalon by a toll free the heads of executive departments and funds telephone call to Western Union at (800) agencies and 300 of the largest cities and 325-a000 (in Misecuri (800) 347ce700), counties to idenufy the Federal agenc:es ron runiussi eserosessAttoes cosefAcT: The Western Union operator should be which would be responsible for Palmer A. Marcantonio, Management given Datagram identification Number overseeing implementation of the "slagle Reform Division. Offlee of Management 3737 and the following message audit" provisions of Circular A-102. and Dudget. Washington, D.C. 20503, addressed to George W. Knightom " Uniform requirements for granta to Telephone:202-306-3067 petitioner's name and telephone State and localgovernments", At the tocal gayernment or other localities number: date petition was mailed; plant same time, he advised executive duiring infonnation about a specific name; and publication date and page departments and agencies and cognizant assignment should contact the number of this Federal Reglater notice. appropriate professional organizadona A copy of the pehtion should also be of the methodology to be used by '* *PedelnlahmWp betwa Seals sent to the Executive legal Director. smaller unifs oflocal government,. d'P*"**"********"""' U.S. Nuclear Regulatory Commission, school districts and special districts'in N if M.fe N #'"$".,sua Washington, D.C. 20558, and to Charles identifying their cognizant agencies, ne a tuinmas wwesenaamedinee itnhu u l [
o 26384 Federal Regi:t Vol. 48, No.110 / Tu:sdry, June 7,1983,.votices present evidence and crossuamine R. Kocher, Esq., Southern California _ recent large i. crease in the number of witnesses. Avenue P.O. Box 800, Rosemead, single audita and thereby needing to Edison Company,2244 Walnut Crove local Covernment umts undertaking if a hearing is requested, the - Commission will make a final California 91770 and Orrick,lierrington establish contact with a cognizant deterniination on the issue of no & Sutcliffe, Attn.: David R. Pigott, Esq., agency, necessitates a dissemination of significant hazards consideration. %e 600 Montgomery Street, San Francisco, the methodology to a wider audience. final determination will serve to decide California 94111, attorneys for the The purpose of this notice is to help when the hearing is held.. licensees. local governments and other localities If the final determination is that the - Nontimely fih.ngs of petitions for leave that have not been assigned a Federal amendment request involves no to intervene, amended petitions, significant hazards consideration, the supplemental petitions and/or te vests cognizant agency identify the Federal Comnussion may issue the amendment for hearing will not be entertame cognizant agency that will be and make it effective, notwithstanding absent a determination by the responsible for administering the single audit' the request for a hearing. Any hearing Commission, the presiding officer or the held would take place after issuance of Atomic Safety and Licensing Board Cities, counties and towns that have the amendment. designated to rule on the petition and/or n t been notified of a cognizant agency If the final detennination is that the request, that the petitioner has made a assignment are assigned to the amendm?nt involves a significant substantial showing of good cause for department or agency that is responsible hazards consideration, any hearing held the granting of a late petition and/or for negotiating their indirect cost rates would take place before the issuance of request. That determination will be under Circular A-87. " Cost principles for any amendment. based upon a balancing of the factors grants to State and local governn ents." Normally, the Commission will not specified in 10 CFR 2.714(a)(1)(iHv) and lf one has been assigned, as listed in the issue the amendment until the 2.714(d). February 28.1980 Federal Register expiration of the 30. day notice period. For further details with respect to this (pages 13396-13408). Cities, counties and flowever, should circumstances change action, see the application for towns not assigned a Federal agency during the notice period such that failure amendment and the licenseca' submittal directly or under Circular A-87 are to act in a timely way would result, for of April 15,1982, which are available for assigned to the Federal agency that example,in derating or shutdown of the public inspection at the Commission's provides the greatest amount of grant facility, the Commission may issue the Public Document Room.171711 Street, funds. license amendment before the N.W., Washington D.C., and at the San School districts 8 are assigned to the expiration of the 30 day notice period. Clemente Library,242 Avenida Del Mar, Department of Education, except for provided that its final determination is San Clemente. California. those in Arkansas, Georgia, Maryland, that the amendment involves no-significant hazards consideration.The Dated at Dethesda, Maryland, this sist day Minnesota. Oregon. Utah, and Puerto of May,19sa. Rico. School districts in those Sta tes and final determination will consider all For the Nuclear Regulatory Commisalon. Puerto Rico are assigned to the c.orie mgMoe, DepanmenMAgricuurm the take t sction, . It will a notice ofissuance and W Ucensing BronchNo.3. D/r/s/on of Special purpose districts are assigned provi for opportunity for a hearing Ucensing. as follows: after tasvance. He Commission expects (R Da aMN N 0-4 at M mut IIousing AgenClas-Dept ofIlousing & that the need to take this action wdl '
- C***
Urban Development occur very infrequently., Transit Agencies-Dept of --~ "N """" " D'"' P "" *" fo'r eave te n us be c w th the Secretary of the Commission, U.S. BUDGET Planning & Development Districts-Dept Nuclear Regulatory Commission, Federal Agencies Responsatzle for of Commerce Washington, D.C. 20555, Attention: Administering Audits of t.ocal Altport Authorities-Dept of Docketmg and Service Dranch, or may Governments and Special Purpose Transportation be delivered to the Commission's Ptblic Districts Document Room,1717 II Street, N.W., Port Authorities-Dept of Washington, D.C. by the above date. AoENCV: Office of Management and Transportation Where petitions are filed during the last fludget. Sewer & Water Districts-ten (10) days of the notice period,it is Action: Notice. Environmental Protection Agency requested that the petitione'r pmmptly so Last year Director Stockman wrote to All Other-Age,ncy providing most grant inform the Commission by a toll. free the heads of executive departments and funds telephone call to Westem Union at (800l agencies and 300 of the lar est cities and 325-4000 (in Missouri (80013474700). counties to ldentify the Fe etal agencies ron runTHen twronenArton costract The Western Union operator should be which would be responsible for Palmu A. Mamantonio, Management given Datagram Idectification Number overseeing implementation of the " single Refonn Division, Office of Management 3737 and the following message audit" provisions of Circular A-102, and fludget, Weshington. D.C. 20503, addressed to George W. Knighton: " Uniform requirements for grants to Telephone:202-395-3687, petitioner's name and telephone State and local governments". At the Local goyernment oriother localities number; date petition was mailed; plant same time, ha advised executive desiring information about a specific name: and publication date and page departments and agencies a1d cognizant assignment should contact the number of this Federal Regleter notice. a propriate tofessional orga. Izations A copy of the petition should also be o the metho ology to be used by 'm epntal m'inone t ews sists sent to the Executive Lasal Dircutor, smaller unifa oflocal 3overn,nent, d*P'""'""*#"**"**""'"**d"*""" U.S. Nudene Mcgulatory Comsnission, school districts and special Jistricts'.in ,'"On*,'N",$,',",5'd*!*' DD, Washington, D.C. 20535, and to Charles identifying tholt cognizant agencies.%e f muins iheir ensniseni eida nepaceitaues. f
j Feder:1 negister / Vol. 48. No.110 / Tuesday, Junu /,1983 / Notic s 26383 adversely affect the state of emergency Technical Specifications (which intervene shall be filed ht accordance preparedness at Nine Mile Point. We presently require immediate corrective with the Commission's " Rules of conclude, therefore, that the licensee's action to return at least one reactor Practice for Domestic Licensing i request for an additional exemption coolant loop to operation) to permit Proceedings"in 10 CFR Part 2. If a should be granted, natural circulation tests to be performed request for a hearing or petition for during the startup test program with no leave to intervene is filed by the above pg reactor coolant loops in operation in date, the Commission or an Atomic Accordingly, the Commission has accordance with the licensees' Safety and Licensing Board, designated determined that, pursuant to 10 CFR application for amendment dated by the Commission or by the Chairman 50.12, the exemption requested by the January 6,1983. of the Atomic Safety and Licensing licensee's letters of August 20 and Before issuance of the proposed Board Panel, will rule on the request October 6,1982, as revised by letter license amendment, the Commission and/or petition and the Secretary of the dated March 9.1983, as discussed will have made findings required by the designated Atomic Safety and Licensing above,is authorized by law and will not Atomic Energy Act of 1954, as amended Board willissue a notice of hearing or endanger life or property or the common (the Act) and the Commission's an appropriate order. defense and security, and is otherwise regulations. In the public interest.The revised The Commission has made a proposed As required by 10 CFR I 2.714. a exemption is hereby granted as follows: determination that the amendment petition for leave to intervene shall set in order to allow for offsite agencies' request involves no significant hazards forth with particularly the interest of the schedular constraints, the next consideration. Under the Commission's petitioner in the proceeding and how emergency preparedness exercise at the regulations in 10 CFR 50.92, this means that interest may be affected by the Nine Mile Point Nuclear Station. Unit that operation of the facility in results of the proceeding.The petition No.1 shall be conducted during the accordance with the proposed should specifically explain the reasons week of September 28,1983. This amendment would not (1) involve a why intervention should be permitted exercise shallinclude appropriate significant increase in the probability or with particular reference to the participation by the State and local consequences of an accident previously following factors:(1) the nature of the authorities. evaluated; or (2) create the possibility or petitioner's right under the Act to be The NRC staff has determined that the a new or different kind of accident from made a party to the proceedyg:(2) the granting of this additional Exemption any accident previously evaluated; or (3) nature and extent of the petitioner's will not result in any significant involve a significant reduction in a proper y financial, or other interest in environmentalimpact and that pursuant margin of safety, the proceeding: and (3) the possible to 10 CFR 51.5(d)(4) an environmental The Commission's proposed effect of any order which may be impact statement or negative determination is based on its finding entered 'n the proceeding on the declaration and environmental impact that the natural circulation tests will be petitionee s interest.The petition should appraisal need not be prepared in conducted using operating procedures also identify die specifb aspect (s) of the connection with this action. that provide compensatory measures subject metter of the proceeding as to that maintain a commensurate level of which petitioner wishes to intervene. Dated at Bethesda, Maryland this 27th day safety as the Technical Specifications Any pere sn who has filed a petition for oNay 1961 that the proposed amendment would leave to intervene or who has been For the Nuclear Regulatory Commissign. temporarily relax. Such compensatory admitted as a party may amend the Robert A. Purple, measures include termination of the test petition vithout requestingleave of the Deputy Director, Dirision oflJcensing. Office and restoration of at least one reactor Board up M fifteen (15) days prict to the o/NuclearReactorRegulation, coolant loop to operation in the event of first prehearing conference scheduled in gra om er rua em ass..l, , abnormal system parameters. the proceeding, but such an amended cooe rees-obal %e Commission is seeking public petition must satisfy the specificity comments on this proposed requirements described above. determination. Any comments received Not later than fifteen (15) days prior to g g g7 within 30 days after the date of the first prehearing conference Southern Cailfornia Edison Co., et al.; publication of this notice will be scheduled in the proceeding, a petitioner Consideration of leeuence of considered in making any final shall file a supplement to the petition to determination.The Commission will not Amendment to Facility Operating - intervene which must include a list of Licenee and Proposed no Significant normally make a final determination the contentions which are sought to be Hazards Consideration Determination unless it receives a request for a litigated in the matter, and the bases for and OpWunity for Hearing h'["g each contention set forth with r ments should be addressed to the %e U.S. Nuclear Regulatory Secretary of the Commission, U.S. reasonable specificity, Contentions shall Commission (the Commission)is Nuclear Regulatory Commission, be limited to matters within the scope of the amendment under consideration. A considering issuance of an amendment Washington,D.C.20555, ATIM to Facility Operating Licanse No. NPF-Docketing and Service Dranch. petitioner who fails to file such a 10, issued to Southern Californi s Edison Dy luly 7,1983, the licensees may file supplement which satisfies these Company, San Diego Cas & Electric a request for a hearing with respect to requirements with respect to at least one Company, the City of Riverside, issuance of the amendment to the contention will not be permitted to Califorata and the City of Anaheim. subject facility operating license and participate as a party. California (the licensees), for operation any persons whose Interest may be nose permitted to Intervene become of the San Onofra Nuclear Centrating effected by this proceeding and who parties to the proceeding, subject to any Station. Unit 2 located in San Die o wishes' to participate as a party in the limitations in the order granting leave to s County, California. proceeding must file a written petition intervene, and have the opportunity to The amendment would grant for leave to intervene. Request for a participate fully in the conduct of the i temporary excep*lons to the facility hearing and petitions for leave to hearing, including the opportunity to
l 0 1 ( [ Federal Register / Vol. 48, No.121/ Wednesday, June 22, 1983 / Notices 28583 South Rose Street. Kalamazoo Michigan
- Metropolitan Edison Company,fersey continued use of a limited numberof 49008.
CentmlPower e Light Company, fuel asamblies which would have either
- FloridaPowerCorporation,etal,.
Pennsylvania Electric Company, and three stainlees steel rods or five Docket No. 504M. CrystalRiver Unit CPUNuclear Corporation, Docket Na stainless steel rods and additional ~ 5048R Three Mile IslandNuclear supporting grid straps in lieu of fuel No.J NuclearGenetutingPlant, Station. Unit Na 2, Dauphin County, rods. . Citrus County, Florida Pennsylvania Date ofpublication ofindividual. Date of amendment request: March 31 1983. Date ofamendment request:May 9. noticein "FedemiRegister": June 1. Briefdescription of amendment:The 1983. 1983. 48 FR 24490.. proposed amendment relates to the Briefdescription of amendment:The Expimtion date ofindividualnotice Cyc?c 5 reload, which has an increased amendment requested would revise the July 2,198.1 cycle lifetime of 480 effective full power Technical Specifications to recognize Local Pub!!c Document Room location: days (EFTD)instead of 350 EFPD in the steam generator tube repair techniques. Multnomah Pub!!c Ubrary,801 S.W.10th previous cycle andinvolves numerical other than plugging. provided such Avenue. Portland. Oregon. changes to the regulating rod group techniques are approved by the . Southern California Edisosi Company, inse Mian limit curves, the axial power , Commission. The licensees application et al, Docket Na 50461, San Onofte shapingend limit curves. the axial. further requested that the Commission Nuclear Cen'emring Station, Unit 2, ' powerhabalance envelope, and othe, approve. within the provisions of the San Diego County, California ' related Technical Specification changes. proposed Technical Specification-Date ofpublication ofindividual revision. the kinetic expansion steam foppM ed. e.. notice in "FederalRqgister": June 8, generator tube repair technique used at January 8,1983.. 1983,48 FR 25292. the facility, thus permitting subsequent Briaf description of amendment Expiration date ofindividualnotice operation oI the facility with the as. [sjCyj}g ecia,g aty excep o ty p July 7,1983. repaired steam generators. (which pneentiy nquin inunediate. lacalPublicDocumentRoom Date ofpublication ofindividual correcun action to nturn at least one, location: Crystal River Pub!1e Ubrary, ~ noticein *'FederalRegister5 May 31 888 N.W. First Avenue, Crystal River. 1983 (48 FR 24231); Notice of Correction reactor coolant loop to operation) to Florida. published June 14.1983 (48 FR 27328), pemit naturelcirculanon tats to be
- 11orida Power & Light Company, Expiration date ofindividualnotica:
periormed during the etartupiest Docket Na 50435, St. Lucie Plant. June 30,1983 (corrected). program with no reactor collant loops in Unit Na 2.St. Lucie County, Florida LccolPublicDocumentRoom operstion,in accordance with the - location: Government Publication licensees application for amendment-v. Date of amendmentrequest: February g, ggg3, Section. State Ubrary o[ Pennsylvania.. dated January 8.1983. Briefdescription ofamendment. . Education *Buildlag. Commonwealth and. Dateofpublicadonofladividual Amendment would permit operation of Walnut Streets. Harrisburg. cein "FederalRegl ster"dilpe 7. St. Lucie Plant. Unit No.1 after deletion Pennsylvania. ExpiroYon dute ofladividualnotice: m of the flux augmentation factor curve
- NortheastNuclearEnergyCompany, from the technical specifications.
et of., Docket Noe. 50-245 and504JdL I"IYI'1888 - LocalPublicDocument' Room
- Date ofpublication ofindividual Millstone NuclearPdwer Station. Unit lo adon: San Clemente Ubeary,242
. notice in "FederalRegister"; lune 3 Nos. 2 and2. New London County,. Avenida Del Mar. San Clemente. Connecticut 1983. 48 FR 25029. Date ofamendmentrequest: February CallIornia. Expiration date ofindividualnotice: July 8.1983. 18,1983. Deted et Betheede. Maryland. thle 14th day LocalPublicDocument Room Briefdescription ofamendment:Tbe oil'** 1**'- locati.,n Indian River Junior College amendments would delete superfluous For the Nuclear Regulatory Commiselon. t' Robert A. Clark Ubrary.3209 VirgInla Avenue. Fort Appendix B environmentaltechnical Pierce. Florida 33450. specifications relative to meterological Chief. Opemting Re6ctor Branch No..f.
- FloridaPower&LightCompany, monitoring. terrestrial monitoring. and Division ofUcensing.,
Docket Na 504J5. St. Lucie Plant, transmission line right of.way- - gra o
- m. w u rs. o e-en e h l e
UnitNo.1, St. Lucie County Florida management.in accordance with the renses-n Date ofamendmertreguestsFebruary licensee's application for amendme.nt 18,1983, dated February 18,1983. [iDochet No.88-38t1 Briefdescription ofamendment: Date ofpublication ofindividual Amendment would permit operetion of notice in "Federo/ Register"' fune 14 SL Lucie Plant. Unit No.1 after. 1983. 48 FR 27328. Southern Californu Edison Co., et at; installation of an improved and larger Explicuon date ofindividua/ notice: Consideration ofle suer Je of capacity 125 volt DC battery system. July 14,1983. Amendment 1o FactRt) wperating Localpublic Doctiment Room Ucense and Prog;osed no Significant amd making necessary changes to the locotton:Waterford Public Ubrary Rope ' Haseres goneideration Dessminetton technicalspeelfication,' ndividual Ferry Roed. Route 158. Waterford, and Opportunity for Hoertng d Date ofpublicadon ofi notice in "redero/ Register"t June 3, Connecticut. ' 1he U.S. Nuclear Regulatory
- Pbrilant CeneralKlectric Capp2ny.
Commlulos(the Ceanaiseloa)la... 1983. 48 FR 2$o27.. Expironon date ofindividualnouce: Docket Na 304H. Tiv]an Nuclear considering iesuance of an amend ~ent Plant, Columbia County, Orupan ~ to Facility Operatir.g Ucense No. NPF-July 8,1983.lic Document Roods LocalPub Date ofamendmenttwqueet:May 2.
- 10. Iesued to Southern California Edison Company. San Diego Cae & Electric location: Indian River junior College 1983.
Ubrary.320e Virginia Avenue. Fort Briefdescripuonof the amendment . Company, the City of Alversida. Pierce. FloHda 33450. The amendment would permit the California and the City of Anahelm.
J ) 28584 Federal Register / VII. 48. N.121/ Wednesd;y, June 22.1983 / N: tic s 4 California (the licensees), for operation issuance of the amendment to the nose permitt'ed to intervene becode 6 of the San Onofre Nuclear Generating subject facill tinglicense and parties to the proceedlag, subject to any a e Persons interest may be limitations in the order granting leave to Station. Unit 2 loosted in San Diego ted by this proceeding and who latervene. and have the opportunity to County. California. wishes to participatass a party la the -
- In accordance with thelisomose's participate fally in the conduct of the request of June 10,1333. 66====h*=*
proceeding must Ale a written petition hearing. indmiing the opportunity to wouldpast a deley of appeenlunately forleave to intervene. Request for a present evidence and crose examine 2% months forthose16monthlaterval hearing and petitions forleave to witnessee. surveillance reqeiraments regarding the latervene shall be Aled in accordance if a hearing is requested, the i reactor protective lastrumentation. with the Conunission's Rulee of Comminion will make a final enginured safety feature actuation Practice for Domestic '#*"7 determination on the issue of no system lastrumentation and accident Proceedingsin 10 CFR Part 2.lf a signincent hasards consideration.%e monlioring lastrussentation which request for a hearing . tition for Anal determination will serve to decide cannot be completed without an leave to latervene is by the above'. when the hearing is held. extended outage in the intervening date, the Commission or en Atomic - - If the Analdeterminationis that the period. Safety and IJcensing Board, designa ted amendment request involves no Before issuance of the proposed by the Commission or by the Chairman significant hazards consideration, the' license amendment, th~e Commission of the AtomicSafe and Licensing Comminion may issue the amendment willhave made Andings requked by the Board Panel, will e on the request and make it effective, notwithstanding Atomic Act of1964 as amended and/or petition and the Secretary of the the request for a h4aring. Any hearing (the Act) the Commission's designated Atomic Safety and Licensing held would take pla6e ener issuance of regulations. Board will issue a notice of hearing or ^ b amendment.... De Commission has ma'de a propowd an appropriate order. If the l'nal deternUnatioh Ii that the determination that b amendrnent As required by 10 CFR 2.714. a amendment involves a signincant request involves no a cant hazards tition for leave to intervene shall set hazards consideration, any hearing held consideration. Under Comminion's orth with particularity the interest of would take place before the issuance of-regulations in to CFR 50.92, this means the petitioner in the proceeding. and any amendment, that operation of the facility in how that icterest ma be affected by the Normally. the Commission will not accordance with the proposed results of the p ing.no petition issue the amendment until the amendment would not:(1) Involve a should specincelly explain the reasons signincant increase la the probability or wh latervention should be permitted ex tretion of the 30 day notice Period. consequences of an accident previous'y wi rticular reference to the H wever. Aould circumstanen chnge during b nok period sud bt faum evaluated; or (2) create.the possibility or folio factors:(1)hnatureof the-to act in a timel weY would result for ' I a new or different kihd of accident fica petitioner's right under the Act to be any accident previously evaluated; or (3) made a to the roceeding:(2) the [* [ f,' ",,0"g ),',*h",tdo 8 e involve a significant reduction in a
- nature an extent o the petitioner's
,y Heense emndmont Wim ee margin of safety. property, financal, or other interest in He Commission's posed the proceeding: and(3) the possible expiration of the 30-day notice period. determinationis base onits finding effectof a order which may be provided that its Anal determination is eat se emndentinwlm no that a delay in the laitial surveillance entered (n e proceeding on the interval of certain surveillances of about petitioner's interest. Re petition Sould sigruficant hasards consideration. W 2% months (from 22% to 25 months)is also identify the specine aspect (s) of the final determination will consider all not significant. compared with b 72-sub ect matter of the proceeding as to
- public and State comments received..
month interval that is required for.the wh petitioner wishes to intervene. Should b Comminion take this action. i lo -term. uilibrium surveillance Any person who has filed a tion for - it will ublish a notice oflesuance and cyc e. Also, quent channelchecks and leave tointervene or who h bun provid for opportunity for a hearing functional surveillances will continue to
- admitted as a party may amend the".
ahe luvance.W Conuninion cts insure operability of the affected petition without requestinaleave of the that the need to take this action wi 1 instrumentation during the extended Board u to fifteen (15) days prior to the occur nry infmquendy. initial surveillance interval that would first pre eering conference scheduled la A request for a hearing or a petition be authorized by the proposed the proceeding, but such an amended for leave to intervene must be filed with amendment.' - - petition must satisfy the specificity the Secretary of the Commission. U.S. The Commlulon is seeking public requirements described above. 3* Nuclear Regulatory Commission, comments on this proposed Not later than fifteen (15) days prioi' to Washington D.C.20668. Attention: determination. Any comments received b first ehearing conference Docketing and Service Br~ench or may within 30 days after the date of schedu! d in the proceeding, a petitioner. be delivered to the Commission's Public publication of this nouce will be shall file a su lement to the petition to Document Room.1717 H Street. NW. considered in ma any final ~ intervene w mustinclude a list of Washington. D.C. by the above date. determination.W ommission will not the contentions which are sought to be Where petitions are Aledduring the last normally make a finaldeterminetion litigated in the matter, and the bans for ten (to) days of the nottoo period it is unless it receives a request for a each contention set forth with requested that the petitioner promptly so hearing. reasonable specificity. Contentions shall inform the Commlulon by a toll fru e Comments should be addresud to the be limited to matters within the scope of teleP one call to Western Union at (800) h Secretary of the Comminion. U.S. the amendment under consideration. A 325-e000 (in Minourt (800) 342-4700). Nuclear Regulatory Commission. petidoner who falls to file such a .Th Western Union operator should be e Washington, D.C. 20655. ATIN: supplement which satisfles these glYen Detegram Identificallon Number Docketing and Service Branch. requirements with respect to at least one 3737 and the following messap By July 22,1983, the licensees may file contention will not be permitted to addrened to George W. Knighton: a requot for a hearing with respect to participate as a party, petitioner's name and telephone --m-
o ( ( Federal Register / Vol. 48. No.121/ Wednesday, June 22, 1983 '/ Notices 28585 number: date petition was mailed: plant staffin its review of applications for For the Nuclear Regulatory Comminion. name: and publication date and page permits and licenses. Patrida A.Comella, number of this Federal Register notice. The draft guide, temporarily identified Acang Diivetor. Division ofHealth. s/t/ng. A copy of the petition should also be
- byits task number.ES 114-4 (which and waste Management. Office o/Naclear sent to the Executive Legal Director.
should be mentioned in all RegulatoryResearch. U.S. Nuclear Regulatory Commission. ~ correspondence concerning this draft in n euem nw ws-en nes =1 Washington. D.C. 20555, and to Charles guide),is entitled " Guidelines for asunacoosr m us R. Kocher. Esq., Southern California Ground. Water Monitoring at In Situ Edison Company,2244 Walnut Grove Uranium Solution Mines" and is POSTAL. SERVICE Avenue. P.O. Box 800. Ro,semead. Intended for Division 3. " Fuels and Cahfornia 91770 and Orrick, Herrington. Materials Facilities."It is being Privacy Act of 1974; Systems of & Sutcliffe. Attn.: David R. Pigott. Esq., developed to provide guidance Records a 9411Y rney for d e acceptable to the NRC staff for ground. AGENCY: Postal Service. 11 r licensees, water monitoring at in situ uranium ACTION: Final Notic'e of Records System Nontimely filings of petitions for leave solutim mines. Change.
- to intervene, amended petitions,
. This draft guide and the associated, suess4ARYt De purpose of supplemental petitions and/or requests value/ impact statement are being issued for.iearing will not be entertained to involve the public in the early stages is to publish final notice of a long-absent a determination by the of the development of a regulatory standing but heretofore unpublished Commission. the presiding officer or the position in this area.They have not routine use which appeared for public Atomic Safety and Licensing Board received complete staff review and do comment in the Federal Register (47 FR designated to rule on the petition and/or not represent an ofBcial NRC staff 16233) of April 15,1982. request, that the petitioner has made a position. EFFECMVE oATE: June 22.1983. o substantial showing of good cause for Public comments are being solicited g,"p 8 M rth th. 24 568 us at te instion t on e d a based upon a balancing of the factors specified in 10 CFR 2.714(a)(1) (IHv) value/ impact statement. Comments on suretsadENTARY W8FORs4AM0ec On April the draft value/ impact statement should 15,1982, the Postal Service published for o er details with respeet to this be accompanied by supporting data. comment in the Federal Register (47 FR action see th l Comments on both drafts should be sent 16233) advance notice of the existence ""li#lLdde a bication for"":i eciaMe' ku M " 1 Pc 2 "'"* % ~ M d a A "a =nts wm mc41vem Postal y""'"c hea dete Commlulon's Public Document Room. Washington.D.C.20655. Attention: e ed is neca sary 1717 H Street. N.W., Washington.D.C., Docketing and Service Branch, by ,g g,, and at the San ClementeIJbrary,242 August 19.1983. De routine use is the result of frequent Avenida Del Mar San Clemente. Although a timelimit is given for requests from Federal. State, and local California. comments on these drafts, comments government agencies for Postal Service , and suggestions in connection with (1) assistance in administering their Deted at Bethesda Maryland.this teth day of June 19s3. Items for inclusion in guides currently programs by furnishing name or address For the Nuclear Regulatory Commission, being developed or (2) improvements in information from Postal Service sources. Victor Necess. all published guides are encouraged at One source for providing this A cting Chief. Licensing Branch No. 3, Division any time, information is rural toute records that n/Licens/ng. Regulatory guides are available for contain customer's names and m emen ruw wwa a* =1 inspection at the Commission's Public addrenes. nenfore, final notice of the u8'o caos tseseas Document Roo.a,1717 H Street NW., routine use and the system to which it Washington, D.C. Requests for single applies follows: UN MM a leeuence and 'g* g],,, f,*[, p ), p, automatic distribution list for single everses Naase: The Nuclear Regulatory Comminion copies of future draft guides in specific Collection and Delivery Records-has issued for public comment a draft of divisions should be made in writing to Rural Carrier Routes. a new guide planned for its Regulatory the U.S. Nuclear Regulatory
- 10. Name and address information Cuide Series together with a draft of the Cor0 mission, Washington D.C.105$5.
ma be disclosed to Federal, State, and d' e e b[)n Attention: Director. Division of local government agencies as required td e and make avsflable to the public TechnicalInformation and Document by such agencies for the purpose of. methods acceptable to the NRC staff of ., Control. Telephone toqueste cannot be performing thalt official duties. Implementing specific parts of that accommodated. Regulatory guides are A complete statement of the system $s Commlulon's regulatione end. la some "'not copyrighted. and Commission.. modified appears below,- ,"l cases, to delineate techniques used by : * *pproval 18 Dot r'9uired to ** produce t the staffin evaluating specific problema ihm. or postulated accidents and to provide ((U,3','C.552(a)). guidance to applicants concerning Deted at Silnr Sprins. Maryland this 15th Collection and Delivery Recordes certein of the information needed by the day ofJune less. Rural Carrier Routes.010.oso.
i <m e eitIs.n cf the U;.it.d st:4...ad a r..ident cf 1e Co.nty. fores.id l.m over the.ge of eighteen e.rs,.nd not a p.rty to or interested in b.beve atitled m.tter.1.m b princip.I sforb of the tinter of Th. Ra.is.or,. newsp per of generel air. ~ ~ ~ ~ * .I. tion, p.blished in.he City of 5. ate Ana, Cooney N# f or.n,.,.nd *.ich n...p.p.c h. be di.doed n$ n...,.,.c of n.r.i.i...i.nen 6, ti,. s rier me,gg,
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the County of San Diego. State of California, A*n """*U*,'.! under the date of March 19,1952, Case {U' n aa8"M8 Number 171349; that the notice, of which W.Icisesan esiis=h se ass the annexed is a printed copy (set in type not smaller than nonpareil), has been published in ""'T,7.Y ".oM sach regular and entire issue of said newspa-g 8'*' " """*' 8 per and not in any supplement thereof on the following dates, to-wit: w so t .......... h.ly. U... 4q w allin the year 1983. .tgy_ __ .gg4 j emespan se
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e Federal Register / Vol. 48. No.191/ Friday, September 30. 1983 / Notices 44953 Chepter I. which are set forth in the For the Nudear Regulatory Commission. will have made findings required by the license amendmenL ue changes to the A. Schwencer. Chief. Atomic Energy Act of 1954, as amended Technical Specifications approved in Ucensing 8moch Nad Division ofucensing (the Act) and the Commission's this amendment are to correct regulations. im u -.s deficiencies and inadv'ertent errors in rm, : %e Commission has made a proposed the Technical Specifications which were determination that the amendment identified during the low power testing request involves no significant hazards period at Crand Culf Unit 1.He Docket Nos. 50-341 and 50-3623 consideration. Under the Commission's corrective measures result as part of the regulations in 10 CFR 50.92, this means review for the full iower operating Southern California Edison Co., et al.; that operation of the facility in i Considerattorwot lasuance of license and are encompassed by the accordance with the proposed prior public notice of the overall action Amendment to Facility Operating amendments would'not (1) Involve a cens*s " P *' 8 f "' involving the proposed issuance of an significant increase in the probability or ,, ds Co dr o operating 1. cense published in the consequences of an accident previously Federal Register on July 28,1978 (43 FR and Opportunity for Hearing evaluated; or (2) create the possibility or 32903)- ne U.S. Nuclear Regulatory a new or different kind of accident from He Commission has determined that Commission (the Commission)is any accident previously evaluated; or (*J the issuance of this amendment will not considering issuance of amendments to involve a significant reduction in a result in any significant environmental Facility Operating Ucenses No. NpF-10. margin of safety, impact other than those evaluated in the and NpF-15 issued t' Southern The Commission has provided a Final Environmental Statement since the California Edison Company. San Diego guidance concerning the application of activity authorized by this amendment Ces & Electric Company, the City of these standards by providing certain is encompassed'by the overall action Riverside. California and the City of examples (48 FR 14870) of amendments evaluated in the Yinal Environmental Anaheim, California (the licensees), for that are considered not likely to involve Statement dated September 1981. operation of the San Onofre Nuclear-significant hazards considerauons. One For further detaus.with respect to this Generating Station.Unita 2 and 3 of the examples relates to a change action, see (1) the applications for the located in San Diego County. California. which either may result in some amendment dated June 9.1983. june 14 (1)In accordance with the licensees
- Increase to the probability or 1983. June 23.1983. june 29.1983. July 19.
requests of Janaury 8. July 14. and consequences of a previously analyzed 1983 August 1.1983. August 9,1983 September 23.1983, the amendments accident or may reduce in some way a August 15.1983, and August 29.1983:(2) would make the following changes: safety margin. but where the results of Amendment No. 9 to Ucense NpF-13 (1) Note 5 la Table 2.2-1 of Technical the change are clearly within all dated September 111983;(3) the Specifications 2.2.11a changed by the acceptable criteria with respect to the Commission's evaluation dated deletion of a description of the specific system or component specified in the September 15.1983:(4) Final Safety methodology used to calculate the Standard Review Plan. Although the Analysis Report (FSAR) and minimum Departure from Nucleate-proposed action may slightly reduce the amendments thereto:(5) Final Boiling Ratio (DNBR) trip setpoint from margin of safety by reducing the margin Environmental Statement dated the safety system settings, to DNBR under some operating September 1981:(6) the Commission's (2) Section B 2.2.1 of the Technical conditions, the safety margin Safety Evaluation Report dated Specifications la modified by the nevertheless remains within accepted September 1981(NUREC-0831) and addition of a description of the specific criteria, as described in Combustion supplements there:to: and (7) the methodology used to calculate the Engineering Topical Report CENPD-225 Commission's Confirmation of Action minimum DNBR trip setpoint from the
- Fuel and Poison Rod Bowing." His letter dated October 20.1982. All of safety system settings.no methodology report was approved by the NRC staff in these items are available for public differs from that deleted from Note 5 of its letter of February 15.1983. C O.
Inspection at the Commission's Public table 12-1 la that it Includes Romas (NRC) to A. E. Scherer (CE). Document Room.1717 H Street. N.W. methodology for incorporation of rod Accordingly, the Commisalon proposes Washington. D.C 20s55, and at the bow penalty factors into the Core to determine that this change does not Hinds fr. College. George M. Mclandon Operating Umit Supervisory System involve a significant hazards Ubrary. Raymond. Mississippi 39154. A (cot.SS) and Core Psotection Calculator consideration. copy of items (1). (2). (3) and (7) may be (CPC) calculations of DNDR. De Commission is seeking public obtained upon request addressed to the (3)%e ACFION statement of comments on this proposed U.S. Nuclear Regulatory Commission, Technical Specification 3/4.2.4 la determination. Any comments received Washington.D.C 20s55. Attention: changed by requiring the plant operators within 30 days after the date of Director. Diviolon of Ucensing. Copies of to " restore" the DNBR to within publication of this notice willbe items (5) and (6) may be purchased at acceptable limita lf it goes outside such considered la making any final current rates ftom the National limits.He present wording requires the determination.De Commission will not . Technicallnformation Service. operators to " reduce" the DNBR to normaUy make a final determination Department of Commerce.8285 Po,rt within acceptable limits ifit goes unless it receives a request for a Royel Road. Springfield. Virginia 22181 outside sue,h !!mits. beering. and through the NRC CPO sales (4) Technical Specifications 4.2.4.4 Comments should be addressed to the i program by writing to the U.S. Nuclear and 8 3/4.2.4 are changed to incorporate Secretary of the Commission. U.S. Regulatory Commission. Attention: revised burnup-dependant DNBR tod Nuclear Regulatory Comunission. Sales Manager. Washington. D.C 20551 bow penalty factors. The tevised factors We shington. D.C 30658, ettru Dochsting CPO deposit account holders may call are based on Combustion Engineering and Service Branch. 301-492-0330. Topical Report CENPD-223. By October 31.1983, the licensees me y Dated at Betheeds. Maryland, this 18th day Before lesuance of the proposed file a request for a hearing with respect of September 19s3. license amendments, the Commission 10 issuance of the amendments to the h t
D I s -) 44954 Federal Register / Vol. 48. No.191 / Friday. SeptImber 30. 1983 / Nstices i subject facihty operating Iloomsee and nose permitted tolatervene become number: date petition was mailed; plant any persons whose interest may be parties to the a _ subject to any name; and publication date and page aRested by this pseemeding and who limitietsome in the ordensenting leave noenber of this Federal Register notice, wiebes to participate as a party in.d.nto late.rvene,and,have w._.d.,t a sA copy of t.he petitles abould misebe ^ ' the j m et me.wrteten to,.r I,.t.fs in o ee.i t. ih. .c eug.iDirector. f forleave tolatervene.Esquest fora hearing, including the opportunity to U.5, NuclearRegulatory thl==la= i j hearing and petitions forleave to. present evidence and crose.e===ina Washington.D.C. mess 'and to Charles ! l Intervene shaR be filed in ecomedance witnesses. R. Kocher. Esq., Southern California with the %==a==in='s " Rules of If ahearingisrequested.the Edison Company.2244 Walnut Crowe r Practice for Domestic Ucensing Commission wi3 make a Avenue.P.O. Box goa, Rosemead. n- - 'in to CFR Part 2. If a determination on the ofno California D1770 and Orrick. Herrington request for a hearing erpetition for algainc==t hasards canalderation.no & Sotcuffe Atta: David R.Pigott.Esq., leave to intervene is filed by the above final determinatica wDI serve to decide 800 Montgomery Street. San Francisco. 'e date, the t'a==3==8aa or en Atomic when b hearing is held. Califomia.96111. attorneys for the l Safety and ucensing Board, designated if the final determination is that the licensees. by the Commission or by the Chairman amendment request involves not Nontimely filings of petitions for leave i of the AtomicSafety and U~aalag significant hazards consideration, the to intervene, amended ~ petitions. Board Panel,willrule on the request Cornmission may issue the amead==nt supplemental petitions and/or vests and/or petition and the Secretary of the and make it effective, notwithstanding for hearing wiB not be enterte 4 i designated Atoaile Safety and Ucensing the request for a hearing. Any hearing absent a determiation by the Board will issue a notice of hearing or held would take plam afterissuance of Comnission, the presiding officer or the an appropriate order. the amendment. Atomic Safety and ucensing Board As required by 10 CFR 2.714, a If the final determination is that the designated to rule on the petition and/or petition for leave to intervene shall set. amendment involves a significant request, that the petitioner has made a forth with particularity the interest of hazards consideration, any hearing held substantial showing of good cause for the petitionarla the proceedmg.and would take plam before the lessence of b granting of a late petition and/or how that laterest may be affected by the any amead==ae request. net determination wiB be results of the proceeding.%e petition Normally, the Co==I== Ion will not ' based upon a balancing of the factors i should specifically explain the reasons issue the amendment until the specified in 10 CFR 2.n4(a)(1)(IHv) and why intervention should be permitted expiration of the 30. day notice period. 2.714(d). with particular reference to the However should circumstances change For further details with respect to this following factors;(1)De nature of the during the notice period such that failure action, see the application for petitioner's right under the Act to be to act in a timely wey would result, for emendment dated January 6,1983 and made a party to the proceedmg:(2) the example. in derating or shutdown of the the supporting SCE letters dated July 14 nature and extent of the petitioner's facility, thera-mi.sion may issue the and September 23.19e3, which are property, financial, or other interest in license amendment before the available for public inspection at the the proceeding; and (3) the possible expiration of the 30 day notice period. Commission's Public Document Room. effect of any order which may be provided that its final determination is 172:' H Street. N.W., Washington. D.C and at the San Clemente Ubrary,242 i entered in the promeding on the that the amendment involves no petitioner's interest. De petition should significant hasards consideration. b Avenida Del Mar. San Clemente, also identify the speciAc aspect (s) of the final determination will consider all California. subject matter of the proceeding as to public and State comments received-Deted at Betheeda Maryload. this mh day j which petitioner wiebes to intervene. Should the Commission take this action, of September.1ses. g Any person who has Aled a petition for it will publish a notice of issuance and For the Nuclear Regulatog Commission. leave to intervene or who has been provide for opportunity for a hearing c,ye W.Kaishima, f I admitted as a party may amend the after issuance.%e Commission expects c3j,f, gj,,,,fn, g,anch No. A Division e/ I petition without requesting leave of the that the need to take this action will ucemias. l Board up to fifteen (15) days prior to the occur very infrequently. %,.,,,,, m, % first prehearing cenference scheduled in A request for a hearing or a petition m e,,, ww the proceeding, but such an amended for leave to intervene must be filed with petition must satisfy the specificity the Secretary of the Commission. US. requirements described above. Nuclear Regulatory Commission. OFFICE OF THE UNITED STATES Not later than fifteen (15) days prior to Washington D.C.20555. Attentiere TRADE REPRESENTATIVE the first prehearing conference Docketing and Service Branch, or may scheduled in the proceeding. a petitioner be delivered to the Commission's Public Advisory Committee for Trade shall file a supplement to the petition to Document Room.1717 H Street. N.W Negotiations; Meeting and i intervene which must include a list of Washington D.C. by the above date. Determination of Closing the contentions which are sought to be Where petitions are filed during the last litigated in the matter, and the bases for ten (to) days of the notice period.lt is %e meeting of the Advisory each contention set forth with requested that the petitioner promptly so Committee for Trade Negotiations (the reasonable specificity. Contentions shall inform the Commission by a toll. free Advisory Committee) to be held be limited to matters within the scope of telephone call to Western Union at (aco) Tuesday October 25,1983, from 120 the amendment underconsiderstion. A 325-4000 (in Missourt (400) 342-4700). p,m. to 420 p.m. at the Federel Home petitioner who falls to file such a ne Westem Union operator should be Loan Bank Board. Amphitheater,will supplement which satisfies these alven Detsgram Identification Number involve a review and discussion of the requirements with respect to at lesst one 3737 and the following message current issues involving the trade policy contention will not be permitted to addressed to George W. Knighton. of the United States.%e review and participate as a party. Petitioner's name and telephone discussion will deal with information iE
.~. _SS400 Federal Ri ter / WL 48, Nr. 246 / Wednieday. Lember 21, issa / Notices 4 i 1 1 NRC E)ososer asso inemant AppucaTione-Consnued '"'" ",,*8,",a *M'@ *" nenes tes n*== caseveresomem 7 _ mia, oss a seat assa a saa passe amense asmse r a= asseum rase amassem.=myw vne mmemmism seat ama meert mesmes suamma ist g(== a em , namu a en. anas, mm. seem at test saap-ameemmensasema nas n n.as,. out e. tese MBastaget noses sw nr assa = ses.musemania on oss n, test osa raisom mm ammase asemm e ste Assemus aos ans,w = means.- rem = m Fisusemas n, q,mus e, r, test seassess(Asimis mm sek amamus e emme esaur amamme ear E"'n". "a"*mu's ser i saammem=g my Dos, tra o= pu.d u-man om n=3 esos remei a ~ Decket No. 56 3e2] present wording requires the operators conditione. the safety margin Southern Cattfornia Edison CompenYe to" reduce" the DNBR to within nevertheless remaine within accepted et a4 Comideradon ofleeuence of acceptable limite if it goes outelde such criteria, se described la Combustion limits. Amendment to FacNNy Operedng 1 hand proposed No Signinoent (4) Technical Speci8catione 4.2.4.4 Engineering Topical Report CENPD-3 255P," Fuel and poison Rod Bowing." a yndComideradon Determinadon and B 3/4.2.4 are changed to incorporate 'Ilife report wee approved by the NRC _,for Heerhg revised, L, '; Ant DNBR rod stasla its lettar of February 15,1983. C. bow penalty factore. h revised factors ~ h U.S. Nuclear Regulatory are based on Combustion M t-, O.Naas (NRC) to A.E.Scherer(CE . Accordingly, the a==i==laa proposee). c Conuelseien (the Coshadesion = ,imuance oran a-)le TopicalReport N asforeleemanos of the pro to detenmine that this change d4es not a-, liconee====d===* the== posed lavolve a algalacant hasards j to Facility Operating IJcease No. NpF. r
==i==ia" consideration. l 15 leeued to Southern California Ediese willhave mada R= mage required by the Company, Sea Diego Cao a Electric Atoade Act of tese, as a==anlad & Commiselonis seeldag public Company, the City of Riverside, (the Act) the===nia=6-t's comument on ele proposed r California and the City of Anaheim, detennimation. Any commente received California (the licensees), for operados % dona, ca==a==8a= bas made a proposed within 30 days after the date of of the Sea Onofra Nuclear Generating deteradaation that the amendment puhucation of thle notice willbe Station Unit 3locatedin Sea Diego request lavolves no signi8 cent hasards ,,,,,aam,,g ga,,g,,, go.g 2 deterssiendon.The===,l==la= wGlnot } County, California. consideration.Undertheca==ianiaa's r i In accordamos with the licensees' reguladenelate CFR sagt, ele means normany make e Baaldeterminados Gos dee facultyla unlessit receives a request for a requeste dJanuary 28, July 14, and September 23.1ges, the amendment p g g. hearing. j would make the followingchanges: gg Comumente should be addressed to the (1) Note a la Tab 2.3-1 of Taeliala=1 lacrossein he probabikty or Secretary of the
===8-=a== U.S. r l Specineation 2.2.2 le by the das sosident previously Nuclear Regulatory ra==ia=ia= degues d a K W aa 6e specinc' (2)meste the poseddHty of Washington, D.C. sossa, Atta: Docketing - used to calculate me a newor dulerent Wd daccmat A'on and Services Branch. m'"'inhaum disparture from Nucleate any accident previously evaluated; or (3) By January 3E 1884, the licensee may Ratio (DNBR) trip setpoint from lavolve a signincast reductionla a Ale a request for a hearing with respect the se ety system settings. margia of eefety, to lescence of the amendment to the (2) Section B 2.2.1 of the Technical & r.--a==aa-has proved subject facility operating license and S eciacetionslemodinedbythe guidamos conosening the appucados of any person whoselaterest may be P addittoo of a descriptica of the speci8c those standards by providing certain affected by this proceeding and who methodology used to calculate the examples (eg FR14370)of amendments wishes to participate as a party la the minimum DNBR trip setpoint hem the that are considered not likely to involve
- ' ;must nie a written petition esfety system settings.The - ""- -- sipificant hasards considerations. One for: leave to intervene. Request for a differe from that deleted hoes Note 8 of, of the====y1a= relates to a change hearing and petitions forleave to i
widek steermay resultla some intervene shau be Aledin eccenlance Tak 2.3-11a that it lacludes lacrease to the pedbebuity or with the a==8==ia='s "Rulee of, l for W# tloa of rod r lune penal @factorelate the Core consequeness of a previously ana' lysed Practice for DomesticIJcensing Opeasties1Jait C. iSystem sosident ormov reducela some way a Proceedings"la 10 CFR Part 2. lf a (COtas) and Core Protection Calculator mesehn,but where the resulte of request for a beerlag orpetitles for the are sleerty within au leave to latervene se Sled by the above (CPC)coloulations of DNBR. l ecoepted artteria with to the date, the Commiselon or en Atonde ( (3)h Astloa statement of Technical systoso or component edla the Safety and IJoensing Beeni, designated Specincetion 3/4,2.4 le ebenged by Standard Review Man, though the by the Comunisolon or by the Cheleman requirlag the sat operators to proposed action may elightly reduce the of the Atomic Safety and ' 5-t; " restore" the to withis neceptah lheite ifit goes outelde such limits. h of eefetyby reduclag the esargia Beerd Penel, willrule on the request { to under some operedag and/or petition and the Secretary or the ( ( f l
Federal Rssister / V
- 48. No. 246 / Wednesday December 2 983'/ N:tices 56461 Ydesignated Atomic Safety and Licensing held would take place after lessence of ' Atomic Safety and Licensing Board the arsendment.,
v &y. designated to rule on the petition and/or~ Board willissue a notice of hearing or ~ If the final detensinationY' that the
==and==at involves a =3snifleant ^b request, that the petitioner has m an appropriate order. hasards consideration. any hearing he% substantial showing of good As required by to CFR 2.714, a m .ld ' the granting of alate petition and/or v-petition for leave to intervene shall set forth with particularity the laterest of would take place before the leeuance of request. net determinationwillbe based upon a balancing of the factors the petitioner in the proceeding and how any ammad==at. Normally,the,===l==fonwillnot specified in to CFR 2.714(a)(110Hv) and e that interest may be affected by the results of the promeding.De petition issue the a=and===r until the 2.714(d).' should specifically explain the reasons expiration of the 30<iay notice period. For furthe'r deta!!s with respect to this why interventius should be permitted However ahould circumstances change action see the application for with particular reference to the during the notice period such that failure amendment dated January 25,1963 and following factors:(1)ne nature of the to act in a timely way would result, for the supporting SCE letters dated July 14 petitioner's right under the Act to be example. In derating or shutdown of the and September 23.1983, which are made a party to the proceeding: (2) the facility, the Commission may issue the available for pubBc inspection at the nature and extent of the petitioner's license amendment before the Commission's Public Document Room, property, financial or other interest in expiration of the 30-day notice period. 1717 H Street. NW., Washington, D.C. the proceeding: and [3] the possible provided that its final determination is and at the SanClemente Library. 242 effect of any order which may be that the amendment involves no Avenida Del Mar. San Clemente, entered in the proceeding on the significant hazards consideration.The California. petitioner's interest. The petition should final determination will consider all Dated at Bethesda. Maryland. this 15th day clso identify the specific aspect (s) of the public and State comments received. omecemk.1983. subject matter of the proceeding as to Should the Commission take this action, For the Nuclear Regulatory Commisaton. which petitioner wishes to intervene. It will publish a notice ofissuance and i G**r8" W. rMa= Any person who has filed a petition for provide for opportunity for a hearing leave to intervene or who has been after isenance.De Commiselon expects Chief N==yRmachNa.f.&risionof cdmitted as a party may amend the that the need to take this action will Lic*a8/A8 petition without requesting leave of the occur veryinfrequently. tFR Du amme rems Sas et mes a=l Board up to fifteen (15) days prior to the A request for a hearing or a petition anAme caos reas.ee.as, first prehearing maference scheduled in for leave to intervene must be filed with the proceeding, but such an amended theSecretaryof the e=nmfasion.U.S. g g r petition must satisfy the specificity Nucles Regulatoey P.a==3==ha requirements described above. Washington.D.C.20555. Attention: TennesseeVeNey Authortty(Brownn Not later than fifteen (15) daya prior to Docketing and Service Branch, or may Ferry Nocieer Plant. Unit 1);- th) first prehearing conference be delivered to the Commi== ion's Public Appecation scheduled in the proceeding, a petitioner Document Room.1717 H Street NW., shall file a supplement to the petition to Washington, D.C., by the above date. Moddication of March 25.1988 Order int:rvene which must include a list of Where petitions are filed during the last Confirming Ucensee N=nie=ents on th) contentions which are sought to be ten (10) days of the notice period. It is Post TMI Related Issues litigated in the matter, and the bases for requested that the petitioner promptly so g each contention set forth with inform the Commission by a toll-free The Tennessee Valley Authority reasonable specificity. Contentions shall telephone call to Western Union at (800) > be limited to matters within the scope of 325e000 (in Missouri (a00) 342-8700). Ofcensee)la the holder of Facility tha amendment under consideration. A The Western Unica operatar should be Operating t tran== No. DPR-33 which petitioner who fails to file such a gf ven Datagram Identification Number authorizes the operation of the Browns supplement which satisfies these 3737 and the following message Ferry Nuclear Plant. Unit t, at steady requirements with respect to at least one addressed to Mr. George W. Knightorg state reactor power levels not in excess contention will not be permitted to petitioner's name and telephone of 3293 megawatts thermal.The facility pcrticipate as a party. numben date petition was mailed; plant consists of a boiling water reactor Those permitted to intervene become name; and publication date and page located at the licensee's site in perties to the proceedmg. subject to any number of this Federal Register notice. 1.imestone County, Alabama. limitations in the order granting leave to A copy of the petition should also be gg int rvene, and have the opportunity to sent to the Executive f.egal Director. On March 25.1983, the Commission l p:rticipate fully in the conduct of the U.S. Nuclear Regulatory Commission, hearing. Including the opportunity to Washington, D.C. 20555, and to Charles issued an Order modifying the license, pr:sent evidence and cross-examine R. Kocher. Esq.. Southern California effective lmmediately. requiring the witnesses. Edison Company,2244 Walnut Grove licensee to implement and maintain if a hearingis requested,the Avenue. P.O. Box 800. Rosemead, certain specific NUREG-0737 items on Commission will make a final California 91770 and Orrick. llerrington dates specified in the Attachments to determination on the issue of no & Sutcliffe. Atta: David R. Pwott Esq., the Order. Among other requirements. significant hazards consideration. The 600 Montgomery Street. San Francisco, the confirrnatory Orde required the final determination will serve to decide California 9411. attorneys for the licensee to install post accident when the hearing is held. licensees. monitoring instrumentation masting the if the final determination is that the Nontimely filings of petitions forleave requirements of items III.t.3. HS.I.4. tmendment request involves no to intervene, amended petitions. and !!T.1.5 of NUREG-0737 during the signihcant hatards consideration, the supplemental petitions and/or requests next tofueling outage. Browns Ferry. Commission may issue the amendment for hearing will not be entertained Unit 1 shut down for the next refueling cnd make it effective. notwithstanding absent a determination by the on April 16.1963-three weeks aiar ths request for a hearing. Any hearing Commission. the presiding officer or the issuance of the Order.Startup was
9 s ( 6 4166 Federal Register / Vol. 49. No. 23 / Thursday. February 2,1984 / Notices Amendment No.8 to Construction Permit Dated at Bethesda. Maryland, this 25th day safety margin but where the results of Nos. CPPR-135 and CPPR-136 and (3) ollanuary 19e4. the change are clearly within all the Commission's related Safety For The Atomic Safety And Ucensing acceptable criteria with respect to the Evaluation. Allof theWeitems are Board. system or component specified in the cvailable for public inspection in the . Marshall E. Miller. Standard Review Plan. Although the Commission's Fublic Document Room, chairman. Administmrivefudge. proposed action increases the time 1717 H Street. NW., Washington, D.C tra on.e.-asei n.4 s i-eues I during which purging is allowed, it does cnd at the Exeter Public Ubrary. Front suses caos new-as not increase the probability of an Street. Exeter. New Hampshire 03833. accident. However, the consequences of item's 2 and 3 may be requested by . 's accident, should one occur during [D t Nos. 50-361 and 50-3621 writing to the U.S. Nuclear Regulatory peging, might be greater than when the Commission. Washington. D.C. 20555. .,outhern California Edison Co. et aL; purge valves are closed. Nevertheten. Attention: Director. Division of Consideration of issuance of the purge system meets staff criteria for Ucensing. Amendments to Faci!!!y Operating closure time in the event of an accident. Dated at Bethesda, Maryland. this 27th day Ucenses and Proposed No Significant which assures that any release under-oflanuary,1964. Hazards Consideration Determination those conditions would be still within For the Nuclear Regulatory Commission. and Opportunity for Hearing acceptable limits. Accordingly, the Commission proposes to determine that George W. Knightoa. The Uy. Nuclear Regulatory this change does not involve a Chiefucensing smach No. 3. Division of Commission (the Commission).is significant hazards consideration. Licensing. considering issuance of amendments to The Commission is seeking public ? I j "*8 "I Facility Operating Ucenses No. NPF-10 comments on this proposed j and NPF-15, issued to Southern determination. Any comments received i California Edison Company. San Diego within 30 day: after the date of ) (Docket No. 50-272-OL.Al Cas & Electric Company, the City of publication of this notice will be Riverside. California and the City of considered in making any final r Public Service Electric & Gas Co. Anaheim. California (the licensees), for determinston.He Commission will not , (Salem Nuclear Generating Station, operation of the San Onofre Nuclear normally make a final determination ~ Unit 1); Onler DWalssing Proceeding Generating Station Units 2 and 3. unless it receives a request for a hearing. I cated in San Diego County. Caliform.a. 1:nuary 25.19s4. Comments should be addressed to the He Commission' published a notice of request of anuary 1 te Secretary of ee Conunluion. ES. - consideratfortof fasuance of an amendments would change the NuclesLr RegulatoryCommission, r.mendment to the Salem facility Technical Specification limit on Washington, D.C. 20555. ATTN: cperting license and a proposed no - operation of the 8-inch containment Docketing and Services Branch. significant hazards consideration purge system from 1.000 hours per 365 file a request for%e licenms may By March 5.1 determination, and an opportunity for a days to 3.000 hours per 365 days. a hearing with respect. hearing, on September 21.1983 (48 FR Before issuance of the proposed to issuance of ee amendments to the 43113-43114).This notice concerned a license amendments, the Commission rt: quested amendment of the technical will have made findings required by the subject facility operating licenses and specifications to permit at seven-month Atomic Energy Act of1954, as amended any person whose interest may be i affected by this proceeding and who cxtension of time for the performance of (the Act) and the Commission's wishes to participate as a party in the J o containment integrated leak rate type regulations. A Test (Technical Specification 4.8.1.2a). De Commission has made a proposed proceeding must file a written petition l l The State of Delaware filed a timely determination that the amendment for leave to intervene. Requests for a j l petition forleave to intervene and request involves no significant hazards hearing and petitions forleave to request for hearing on October 21.1983. consideration. Under the Commission's intervene shall be filed in accordance with the Commission's " Rules of j %e NRC Staffissued the requested regulations in 10 CFR 50.92, this means tmendment on October.31 1983. By an that operation of the facility in Practice of Domestic Ucensing Order entered November 17.1983, the accordance with the proposed Proceedingsin to Cm Part 2. lf a l Board granted the intervention petition, amendments would not (1) Involve a request for a hearing or petition for cnd directed the State of Delawa're to significant increase in the probability or leave to intervene is filed by the above file a supplement to its petition setting consequences of an accident previously date, the Commission or an Atomic firth at least one contention cognizable evaluated; or (2) create the possibility of Safety and ucensing Board, designated under10 CR 2J14(b). by January 4. a new or different kind of accident from by the Commission or by the Chairman l 1984.That date was extended by two any accident previously evaluated: or (3) of the Atomic Safety and Ucensing l weeks upon motion. involve a significant reduction in a Board Panel, will rule on the request l On January 20.1984, the State of margin ofsafety. and/or petition and the Secretary or the Delaware filed a motion to withdraw its The Commission has provided designated Atomic Safety and 1.icensing petition. no supplement having been guidance concerning the application of Board willissue a notice of hearing or filed. Hat motion is granted and the these standards by providing certain an appropriate order. Intervention petition is withdrawn. examples (48 FR 14870) of amendments As required by 10 CFR 2.714. a Inasmuch as there are no other that are considered not likely to involve petition for leave to intervene shall set intervention petitions or requests for significant hazards considerations. One
- f. orth with particularity the interest of hearing in accordance with the of the examples (vi) relates to a change the petitioner in the proceeding and how Commission's notice, the matter is which either may result in some that interest may be aifected by the uncontested, and the adjudicatory increase to the probability or results of the proceeding.The petition Proceeding is therefore Dismissed.
consequences of a previously. analyzed should specifically explain the reasons It is so Ordered. accident or may reduce in some way a why intervention should be permitted l
t ) .Y v b Federal Register / Vol. 49. No. 23 / Thursday. February 2.1984 / Notices 4167 with particular reference to the notice period such that failure to act in a amendment dated January 3,1984, following factors:(1)The nature of the timely way would result for exemple,in which is available for public inspection petitioner's right under the Act to be derating or shutdown of the facilities. at the Commission's Public Document j made a party to the proceeding: (2) the the Commission may issue the license Room.1717 H Street. NW Washington. 1 nature and extant of the petitioner's amendments before the expiration of the D.C. and at the San Clemente ljbrary. ) property, financial, or other interest in 30-day notice period, provided that its 242 Avenida Del Mar. San Clemente, the proceeding: and (3) the possible final determination is that the California, effect of any order which may be amendments involve no significant Dated at Bethesda, Maryland, this 30th day entered in the proceeding on the hazards consideration.He final of January.19s4. 1 petitioner's interesL The petition should determination will consider all public For the Nuclear Regulatory Commission. also identify the specific aspect (s) of the and State comments received. Should subject matter of the proceeding as to the Commission take this action,it will h ens B neh No..t. Division of ' g which petitioner wishes to intervene. publish a notice of issuance and provide
- "##"8 Any person who has filed a petition for for opportunity for a hearing after leave to Intervene or who has been issuance. ne Commission expects that I"'"-''"'d*+****'"!
""'*C"'""'*" admitted as a party may amend the the need to take this action will occur .L petition without requestingleave of the very infrequently. p Board up to fifteen (15} days prior to the A request for a hearing or a petition DockoN !,0-280 t first prehearing conference scheduled in for leave to intervene must be filed with ? the proceeding, but such an amended the Secretary of the Commission. U.S. Virginia Electric and Power Co. petition must satisfy the specificity Nuclear Regulatory Commission. Grantingof Rollef From ASMESection requirements described above. Washington, D.C. 20555. Attention: XIInservice Testing Requirements ~ Not latpr than fifteen (15) days prior to Docketing and Service Branch. or may 3 J the first prehearing conference be delivered to the Commission's Public ne U.S. Nuclear Regulatory scheduled 1a the proceeding. a petitioner Document Room.1717 H Street. NW, Commission (the Commission) has e shall file a supplement to the petition to Washington.D.C., by the above date. granted relief from certain requirements intervene which must include a list of Where petitions are filed during the last of the ASMECode.SectionXI.** Rules the contentions which are sought to be ten (10) days of the notice period. it is for Inservice lospection of Nuclear litigated in the matter, and the bases for requested that the petitioner promptly so Power Plant Components" to Virginia each contention set forth with inform the Commission by a toll-free Electric thd Power Company.ne relief reasonable specificity. Contentions shall telephone call to Western Union at (800) relates to the inservice inspection [ be limited to matters within the scope of 325-6000 (in Missouri (800) 342-6700). program for the Surry Power Station the~ amendments under consideration. A
- ne Westem Union operator should be Unit No.1 (the facility) located in Surry p
petitioner who falls to file such a given Datagram Identification Number County Virginia.De ASMECode supplementivhich satistfies these 3737 and the following message requirements are incorporated by y requirements with respect to at least one addressed to George W.Knighton: reference into the Commission's rules contention will not be permitted to petitioner's name and telephone and regulations in to CFR Part 50.The 4 l participate as a party. number; date petition was mailed; plant relief is effective as of January 25.1984. Those permitted to intervene become name; and publication date and page ne relief permits the licensee to j parties to the proceeding. subject to any number of this Federal Registar notice. perform certain inservice inspections in limitations in the order granting leave to A copy of the petition should also be a manner different from that prescribed intervene, and have the opportunity to sent to the Executive Legal Director, in Section XI of the ASME Boiler and g;[ participate fully in the conduct of the U.S. Nuclear Regulatory Commission. Pressure Vessel Code and applicable hearing, including the opportunity to Washington. D.C. 20555. and to Charles Addenda, as required by 10 CFR 50. present evidence and cross-examine R. Kocher. Esq:. Southem California because of inacce saibility, configuration y; witnesses. Edison Company. 2244 Walnut Grove of components, radiation level, or other If a hearing is requested. the Avenue. P.O. Box 800. Rosemead, lid '' "'s Commission will make a final California 91770 and Orrick. Herrington determination on the issue of no ar Sutcliffe. Attentiort David R. Pigott. ', quest for lief omph.es w h da 9 sigmficant hazards consideration. The Esq 600 Montgomery Street. San final determination will serve to decide Francisco, California 94111 attorney for Atomic Energy Act of 1954.,as amended (the Act). and the Commission,s rules when the hearing is held. the licensees. ,i If the final determination is that the Nontimely filings of petitions forleave and regulations. The Commission has made appropriate findings as required Ii amend:ngnt requests involves no to intervene, amended petitions. l *[ significant hazards consideration. the supplemental petitions and/or requests by the Act and the Commission's rules Commission may issue.the amendments for hearing will not be entertained and regulations in 10 CFR Chapter I. and make them effective. abseat a determination by the which are set forth in the letter granting reffef. notwithstanding the request for a C6mmission, the presiding officer or the The Commission has deterrc.ined that hearing. Any hearing held would take Atomic Safety and Licensing Board place afterissuance of the amendments. designated to rule on the petition and/or the granting of this relief will not result if the final determination is that the request, that the petitioner has made a in any significant environmental impact amendments involves a significant substantial showing of good cause for and that pursuant to 10 CFR 51.5(d)(4) hazards consideration, any hearing held the granting of a late petition and/or an environmentalimpact statement or wocid take place before the issuance of request.That determination will be negative declaration and environmental any amendments. based upon a balancing of the factors impact appraisal need not be prepared Normally, the Commission will not specified in to CFR 2.714(a)(1) (i}-(v) in connection with issuance of this issue amendments until the expiration of and 2.714(d). relief. the 30-day notice period. However. For further details with respect to this For further details with respect to this should circumstances change during the action, see the application for action. see (1) the application for relief
,0. Is)hb 3 UNITED STATES NUCLEAR REGULATORY COMMISSION TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICEMSE AND PROPOSED NO !!G!!IFICA?!r uA7Aggs CONSIDERATION DETE"J.I!!ATION AND OPPORTUuITY FOR HEARING The U. S. Nuclear Regulatory Comiss< ion (the Comission) is considering issuance of an amendment.to Facility Operating License No. DPR-33, issued to Tennesse2 Valley Authority (3he licensee), for operation of the Browns 9 Ferry Nuclear Power Plant, Unit No.1, _ located in Limestone County, Alabama. The amendment would revise the Technical Specifications (T.S.) of the operating license to: 1). modify the rore physics, thermal and hydraulic limits to be consistent with the reanalyses associated with replacing about _ 1/3 of the core during the curr'ent refueling outage and 2) reflect plant modifications performed during the current refueling and mcdification outage, which started on April 16, 1983. Specifically, the amendment would result in changes to the T.S. in the following eleven areas: 1) Changes to the license related to the Cycle 6 core reload involving removal of depleted fuel assemblies in about one-third of the nuclear reactor core and replacement with new fuel of the same type previously loaded.in the core with attendant license changes in the core pr tection safety limits and reactor protection system setpoints. The actual changes are a slight adjustment (by 0.01 in initial core life) in the Operating Limit Minimum Critical Power Ratio (0LMCPR), an added table on maximum average planar linear heat generation rate (MAPLHGR) versus average olanar exoosure and a change to the bases for the total relief capacity of the safety relief valves.
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s, .2) Changes to the T.S. to revise the tables listing surveillance instrumentation for suppression pool bulk temperature reflecting the in-stallation of 16 sensors for an improved torus temperature monitoring system and a revision to the basis for the existing limits on torus water temperature; 3) Changes to the T.S. to reflect modifications to the scram discharge volumes (SDV), and the addition of a second scram discharge instrument volume (SDIV); each of the SDIVs now have redundant vent and drain valves and new, diverse level instrumentation. The changes,to the T.S. are to add operability, surveillance and calibration requirements on the new level instrumentation and valves. 4) Changes to T.S. su eillance instrumentation tables to add new instrumentation for containment high-range radiation monitors and to add new instrumentation, and delete current instrumentation for,dyrwell pressure-wide range and suppression chamber wide-range water level in response to requirements in NUREG-0737,; items II.F.1.3, II.F.1.4 and II.F.1.5. 5) T.S. changes to incorporate calibration and surveillance requirements ~ for time delay relays to prevent spurious isolativn of the HPCI and RCIC systems.as required by NUREG-0737; item II.K.3.15. 6) Revision of the T.S. table for containment isolation valve surveillance to add two new isolation valves that are p' art of a newly installed redundant cisenarge line from the drywell compressor into containment; 7) Revision of the T.S. to reflect installation of strong backs on personnel airlock doors to allow testing in accordance 'with 10 CFR Part 50, Ap;:endix J;
m 8) Revision of T.S. to provide limiting conditions for operation and surveillance requirements for electric power monitoring for the reactor protection system power supply; 9) Modify the T.S. to apply to the new analog (continuous measuring) instrumentation. The analog instrumentation replaces certain mechanical-type pressure and level switches with a more accurate and more stable elec-tronic transmitter / electronic switch system and will provide improved performance of trip functions for reactor protection system actuation, and ~ containment isolation. The changes to the T.S. include: a. in the tables on functional test frequencies,- calibration frequencies and surveil' lance' requirements, for each switch replaced, add'the instrument number and type of sensor beneath the parameter being monitored and/or controlled. b. add notes to the above tables to specify how the functional and calibration tests are to be conducted. in addition to the above administrative changes, the calibration c. - requirements have been changed to incorporate extended calibration intervals. However, the required setpoints, functional test fre-quencies and channel check frequencies for the instrumentation will not be changed. The new calibration requirements, together with the new instrumentation, are expected'to provide a more reliable instrumentation system. 10) Change the T.S. to reflect the addition of a thermal power monitor. The purpose of this monitor is to have the Average Power Range Mcnitor (APRM) flow biased neutron flux signal respond to the thermal flux rather u
y -4 than the neutron flux in the ' core by accounting for the, approximately 6-second thermal time constant of the fuel. The specific changes to the T.S. are: a. Add the words " flow biased" in parenthesis to the heading to the heading for the limits on "APRM Flux Scram Trip Settings" to indicate that the settings are reduced according to the equations given in.this section when there is less than 100% core ficw. b. -Thdre is a trip unit-separate from the APRM flow-biased scram at less than 120% instantaneous neutron flux., A new requirement is being added to require that whenever the mode switch is in the run position, the APRM fixed high' flux scram trip setting shall be operable and' set at S 120% power. c. The bases for the neutron flux scram are revised to describe the ~. functions ~of the APRM Flow-Biased High" Flux Scram, Trip Setting and -the Fixed High Neutron Flux Scram Trip. d. Since there is new a new trip system, the tables listing the operability requirements and functional test frequencies on the scram instrumentation have to be revised to add, this 'new instrumentation. 11) Administrative changes to the T.S. involving changes to the Table of Contents to reflect. the above license changes, an editorial change and cor-rections to the list of' sample valves to be consistent with present plant configuration.- These revisions to the Technical Specifications would be made'in . response to the-licensee's application dated July 13, 1983, as supplemented July 21, 1983. s
Before issuance o'f the proposed license amendment, the Commission will have made findings as required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations. The Comission has made a proposed determination that the amendment request. involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident pre-vicusly evaluated; or (2) create the possibility of a new or different kind of accident frem any accident previously evaluated; or (3) involve a significant reduction in a margin of. safety. The Comission has 'provided guidance concerning the application of the standards by providing examples.of actions that are likely, and are not [ likely, to involve significant hazards. considerations (48 FR 14870). The ~ first three examples of actions not likely to involve significant hazards censiderations are: "(i) A purely administrative change to technical specifications: for example, a chan~ge to achieve consistency throughout the, technical specifi-cations, correction of an error, or a change in nomenclature. (ii) A change that constitutes an additional limitation, restriction, or control not presently included in the technical 'specif.ications: for example, a more stringent surveillance requirement. j (iii) For a nuclear power reactor, a change resulting from a nuclear reactor core reloading, if no fuel assemblies significantly different? from .those found previously acceptable to the NRC for a previous core at the r.
facility in question are involved. This assumes that no significant changes. are made to the acceptance criteria for the technical specifications', that the analy'tical methods used to demonstrate conformance with the technica.1,. specifications and regulations are not significantly changed, and that NRC has previously found such methods acceptable." Each of the eleven changes to the T.S. described previously is encompassed by one of the above examples of actions not likely to involve a significant hazards consideration. The basis for the staff's determination on each of the eleven changes is discussed below. 1. Core. Reload The changes to the T.S. associated with removing depleted spent fuel from the reactor and replacing these with new fuel assemblfes is encompassed by example (iii) above of those actions not likely to involve a'significant hazards consideration. The proposed reload involves fuel assemblies of the same type as .previously found acceptable by the staff and loaded in the core in previous. cycles. The analytical methods used by the licensee to demonstrate conform-ance to the tech'nical specifications have been previously approved by the staff. In addition, no changes have been made to the acceptance criteria for the technical specification changes involved. Since the replacement fuel assemblies'are of the same type previously added to all three Browns Ferry units and other BWRs and since the codes, nodels and analytical techniques used to analyze the reload have been generically approved.by the NRC, the changes to the T.S. associated with the reload are clearly enccmaassed by example (iii) of the guidance provided ~ _
~ by the Comission for an action not likely to involve a significant hazards consideration. 2. Changes Related to Torus Modifications On January 19, 1982, the Commission issued an Order in the matter of Brcwns Ferry Unit I requiring completion - during the current refueling outage - of the plant modification required by the Mark I program so as to comply with the Staff's Acceptance Criteria contained in Appendix A to NUREG-0661. Numerous modifications are being implemented in the Unit 1 torus during the reload 5 refueling outage as part of the Mark I Containment Program. These redifications are required by NRC to restore the originally intended margins of safety in the containment des'ign.- Most of the major internal structural modifications to the torus were completed during the previous refueling outage. These modifications are discussed in Amendment No. 76 to Facility OperatingLicenseNo.DPR-33issuedSeptemberi5,1981. The modifications being made during this outage will complete the requirements specified in NUREG-0661, " Safety Evaluation Report, Mark I Containment Long-Term' Program." One of the changes to the T.S. is to revise the tables that list the surveillance instrume.,tation associated.with the suppression pool bulk temperature. This modification provides an improved torus temperature monitoring system which consists of 16 sensors. This will provide a more accurate indication of the torus water bulk temperature as required by NUREG-0661 and will replace the suppression chamber water temperature instruments presently listed in the T.S. Another change to the T.S. is to revise the bases for the present limits on temperature of water in the torus. The present bases for
suppression pool temperature limits were founded on.th,e Humboldt Bay and Bodega Bay tests. Consistent with the long-term torus, integrity program of NUREG-0661 and NUREG-0783, the baces require change to account for steam mass fluxes through the safety / relief valve (S/RV) T-quenchers. The proposedLbases describe assurances of stable and complete condensatina of stean discharged through the S/RVs and adequate residual heat removal (RHR) and core spray pump net positive suction head. As noted above, the femmission ordered that the above torus modifications be implemented.' The changes to the T.S. are necessary admin-istrative follow up actions essential to the implementation of these improvements. The changes to the T.S. place operability and calibration requirements on the new' temperature monitoring system. Since these are new instruments, the surveillance requirements are not presently in the T.S. Thus, adding these restrictions and controls is encompassed by example (ii) provided by the Comission. The bases for the suppression pool temperature limits are also being changed to account for steam mass fluxes through the safety relief valve -T-quencher. as ' required by NUREG-0661 and NUREG-0783. The proposed bases describe assurances of stable and complete condensation of steam discharged through the S/RVs and adequate RHR and core spray pump net positive suction head. The changes, are necessary administrative follow up action essential to the implementation of improvements required by the Ccmmission. Modifying these restrictions is encompassed by example (ii) provided by the Commission. 3. Scram Discharge Instrument Volume The SDVs and SDIVs are being modified to address inadequacies ice.9tified by the partial rod insertion event on Browns Ferry Unit 3 in June 1980. One
of the modifications includes adding another valve in series to the existing drain and vent valves on the SDV and SDIV. Another modification includes adding electronic level switches to initiate a scram on a high level in the SDIV. On June 24, 1983, the Comission issued Orders for the Browns Ferry Nuclear Plant, Units 1 and 3 to install permanent Scram Discharge System modifications during the Cycle 5 outages for Units 1 and 3. (This is the Cycle 5 outage for Unit 1.) The modifications have been previously com-pleted for Unit 2. The Orders included "Model Technical Specifications which are provided as guidance for preparing Technical Specification changes that will be required to be approved before operation with the modified system." Both the modification of the systems and submission of T.S. changes to-place operabi'lity and surveillance requirements on the new instruments and valves were required of the licensee to be in compliance with a Ccmission Order. 'Thus, the changes to the T.S. are necessary admin- ~ istrative follow up actions essential to.the implementation of these improvements. Adding these new restrictions and controls, which otherwise would not be in the T.S., is encompassed by example (ii) of the guidance prcvided by the Commission. 4 Accident Monitoring Instrumentation Item II.F.1 of NUREG-0737,* " Clarification of TMI Action Plan Requirements," requires all licensees to install five new monit'oring systems and to provide onsite sampling / analysis capability for a specified range of radionuclides. For all six categories, NUREG-0737 states: " Changes to technical specifi-cations will be required." During this refueling outage, the licensee has installed: a) a containment high-range monitoring system, b) a drywell
wide-range pressure monitoring system and c) a suppress.fon chamber wide-range water level monitoring system. These three items were required by NUREG-0737', items II.F.1.3, II.F.1.4 and II.F.1.5, respectively. The change's to the T.S., which track the model -T.S. provided to the licensee by the~ staff, are to add operability and surveillance requirements on the new monitoring systems to the T.S. The revisions also delete the present drywell pressure and suppression chamber watir level instruments since they are being replaced by items b and c above. The changes to the technical specifications,are necessary admin-istrative follow up actions required by the Ccmission. Adding the new surveillance requirements and controls *is encompassed by example (ii) of the guidance provided by' the Comission. 5. NUREG-C737, Itsm II.K.3.15 TMI Action Plan Item II.K.3.15 requires licensees.of BWRs to modify pipe-break-detection circuitry so that pressure spikes result'ing from high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) initiation will not cause inadvertent system isolation. The licensee elected to employ the BWR Owners Group modification whic.h incorporates a three-second time delay relay (TDR) to prevent' spurious isolation. In our letter to the licensee of October 13, 1981, we requestad the licensee to provide certain analyses and to " propose the appropriate Surveillance Requirements and Limiting Conditions of Operation for th'e HPCI and RCIC systems which address this item." The safety evaluation was previded by the licensee's letter of December 16, 1981. All of the Browns Ferry units have had a three-second TDR on the HPCI system. During the current outace for Browns Ferry Unit 1, a TDR was added to the RCIC systen. The proposed changes
T ~ to the Technical Specifications requiring calibration and surveillance of the time delay relays is in accordance with the requirements of NUREG-0737, item II.K.3.15 and the staff's follow up letter. The changes to the T.S. are necessary administrative follow up actions essential to the implementa-tion of these improvements. The addition of requirements in the T.S. for the operability and surveillance of the new time delay relays clearly imposes additional limitations and controls not presently included in the T.S. and is therefore encpmpassed by example (ii) of the guidance provided by the Commission. 6. Redundant ' Air Sucolv to Dr_well During the current outage, TVA has installed a second discharge line frem the drywell compressor i'nto containment. This line was added to provide the capability for isolation of approximately one-half of the drywell sup- '. pression equipment in tne case of a drywell line leak. This air supply will be used.to supply two inboard main steam isolation valves (MSIVs), approxi-mately one-half of the main steam relief valves (MSRVs),.an'd approximately one-half of all other air-operated equipment in the drywell. This will ~ significantly reduce the possibility of any one control air pipe break inside containment from requiring immediate shutdown and isol tion due to MSIVs, MSRVs, and drywell coolers being inoperable. Since any line penetrating containment requires two isolation valves, the table in the Technical Speci-fications listing the isolation valves that must be periodically tested is being rev.ised to add these two new isolation valves. TVA has concluded that this modification will increase the margin of safety. The changes to the technical specifications are necessary administrative follow up actions essential to the implementation of this impr.ovement. The two isolation [
valves being added.to the T.S. are new val) s not presently listed in the x T.S. If they were not added to the table of valves to b.e periodically tested, there would be no T.S. requirement to test.these valves. Adding these ad-ditional controls is encemnassed by example (ii) of the guidance provided by the Comission. 7. Modification of Airlock Doors Section III.D.2(b) of Appendix J,10 CFR Part 50, requires that air locks shall be tested at 6 month-intervals at an internal pressure not less than P P is defined as "the calculated peak containtrent internal pressure a. 3 related to the design basis accident and specified either in the technical specification or associated bases." Rbactor plants designed prior to the issuance of Appendix J o'ften do not have the capability to test airlocks at P, without the installation of strongbacks or the performance of mechanical adjustments to the~ operating mechanisms of the inner doors. The reason for this is that th,e inner doors are designed to seat with hccident pressure on the containment side of the door, and therefore, the operating mechanisms were not designed to withstand accident pressure in the opposite direction. When-the airlock is pressurized for a local airlock test. (i.e., pressurized between the doors), pressure is exerted on the airlock side of the inner door, causing the door to unseat and preventing the performance of a mean-ingful test. The strongback or mechanical' adjustments prevent the unseating of the inner door, allowing the test to proceed. Section 4.7.A.2.g of the present T.S.' requires that "the personnel air lock shall be tested at a pressure of 49.6 psig during each operating cycle." The proposed chance to the T.S. is to require that "the personnel air lock shall be tested at 6-month intervals at an internal pressure of not less than 49.6 psig." This
I r more stringent surveillance requirement is clearly encompassed by example (ii) of' ths guidance provided by the Comission'. 8. Monitorino of RPS_ Power Sucoly By letter dated August 7,1978, we advised TVA that during review of Hatch Unit 2, the staff had identified certain deficiencies in the design of the voltage regulator system of the motor generator sets which supply power to the reactor protection system (RPS). Pursuant to 10 CFR 50.54(f), tvd was required to evaluate the RPS power supply for Browns Ferry 1, 2 and 3 in light of the information set forth in our letter. Based on our review of TVA's response, by letter dated September 24, 1980, we informed TVA (and most other BWRs) that "we have detemi'ned that modifications should be per-f.ormed to provide fully' redundant Class IE protection at the interface of non-Class IE power supplies and the RPS." We also advised TVA that."we have found that the conceptual design proposed by the General Electric Company and the installed modification on Hatch are acceptable solutions to our concern." By letter dated December 4, 1980, TVA committed to install the required modifications. By letters dated October 30, 1981 and July 28, '1982, we sent TVA model Technical Specifications for electric power moni-toring of the RPS design modification. During the current outage of Unit 1, the RPS is being modified to provide a frily redundant Class IE protection at the interface of the non-Class IE power supplies and the RPS. This will ensure that failure of a non-Class IE reactor protection power supply will not cause adverse interaction to the Class IE reactor protection system. The Technical Specifications are being revised similar to the model T.S. provided to TVA to reflect the limiting conditions for operation and surveillance requirements associated with the RPS modifications. Page 42
is being modiffed to add a description of these sections in the bases. The changes to the T.S. are necessary= administrative fol. low up actions essential to the implementation of these improvements. The additional limi-tations and controls, which are presently not in the T.S., are encompassed by example (ii) of the guidance provided by the Commission. _9. Analoc Trip' System The RPS, the primary containment isolation system (PCIS), and the core standby cool'ing systems (CSCS) use mechanical-type switches in the sensors that monitor plant process parameters. These mechanical-type switches are verysubjecttodriftintheset-pointasisevidentfromtheManylicensee event reports (LERs) that have been submitted reporting calibration drifts in these switches. Advarices in technology make it possible to replace the mechanical- ~ type switches with a more accurate and more stable electronic transmitter / electronic switch system. For several years, TVA has been planning to replace existing pressure switches that sense drywell and reactor pressures with analog loops and modify the reactor water level indication loops to improve the reliability, ~ accuracy and response time of this instrumentation. l The modification involves removing one device and substituting.other devices to perform the same function. Changes in design bases, protective function, r redundancy, trip point.and logic are not involved. Similar modifications have been approved for other SWRs. As described previously, most of the j changes to the' T.S. are administrative in nature (i,.e., adding the specific i number and types of sensor and adding notes to describe how testing is con-ducted). As such, they are enccmpassed by example (i) of the guidance provided by the.Comission. The changes in surveillance recuirements l b
relate to example (ii) of the guidance provided by the Commission. Some of the surveillance intervals have been decreased as appropriate for each ~ new instrument. However, the overall effect of the changes in technical specifications will be to increase the total surveillance requirements in support of a more reliable instrumentation system.
- 10. Thermal Power Monitor During.this outage, the licensee is installing a flow-biased simulated thermal power monitor. These monitors are installed on most all BWRs; the justification for these monitors is discussed in the " Bases" for the APRM settings in the BWR Standard Technical Specifications, NUREG-0123 (BWR/4, STS, Section 2.2.1, page B2-7). 'The m6nitors are installed to have the APRM flow-biased neutron' flux signal respond to the thermal flux rather
? than the neutron flux by accounting for the approximately 6-second thermal time constant of the fuel. The addition of the themal power monitor will prevent a flow-biased neutron flux scram when a transieht-induced neutron flux spike occurs that is a short time duration and does not result in an instantaneous heat flux in excess of transient limits. Neutron flux is I damped by approximately a 6-second fuel time constant...This featurr. will reduce the number of scrams due to small fast flux transients such as those which result from control valve and MSIV testing and small perturbations in water level and pressure. A themal power monitor was installed in Browns Ferry l' nit 2 during the last outage and approved by Amendment No. 85 to Facility Operating License No. OpR-52 issued March 11, 1983. As identified previously, the changes to the T.S. are to add operability and functional test frequency requirements for this new trio f l
system and to add a description of this new trip system,in the " Bases." g The changes to the T.S. are necessary administrative follow up actions essential to the implementation of these improvements. The additional limitations, restrictions and controls, which are not presently included in the T.S., are encompassed by example (ii) of the guidance provided by the Comission.
- 11. Administrative Changes Several administrative changes are being made to the Technical Specifications.
These include revising the Table of Contents to reflect the changes discussed above, an editorial change and corrections to the list of sample valves <to reflect *the corrent plant configuration. These changes are editorial in' nature and have no safety significance. These changes are encompassed by example (i) cited by the Comission as an action h not likely to pose a significant hazards consid'eration. Since all of the changes to the T.S. are enccmpasshd by an example in the guidance provided by the Comission of actions not likeiy to involve a significant hazards consideration, the staff has made a proposed determina-tion that the application for amendment involves no signific3nt hazards consideration. The Comission is seeking public coments on this proposed determination. Any, coments received within 30 days af ter 'the date of publication of this notice will be cc.7sidered in making any final determi-nation. The Comission will not normally make a final determination unless it receives a request for a hearing. k.__
9 - -Y- 'Coments should be addressed to the Secretary cf the Comission, U. S. Nuclear Regulatory Comission, Washington, D. C. 20555, Attn: i .Docketin'g and Service Branch. By November 23, 1983, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this preceeding , and who wishes to participate as a party in the proceeding must file a written petition for leave,to intervene. Request for a hearing and peti-tions for leave to intervene shall be filed in accordance with the Cemission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. If a request for a hearing or petition for leave to inter-i vene is filed 'by the abo'e date, the Comission or an Atomic Safety and v Licensing Board, designated by.the Comission or by the Chairman of the ~. ~ Atomic Safety and Licensing Board Panel, will rule on the request and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue 1 notice of hearing or an appropriate order. 1 l As required by 10 CFR 52.714, a petition for leave to intervene shall set forth with giarticularity the interest of the petitioner in the proceed-ing, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to'the following factors: (1) the nature of the petitioner's right under the Act to be mace a party to the. proceeding; (2) the nature and extent of the petitioner's property,, l financial, or other interest in the proceeding; and (3) the possible effect cf any order which may be entered in the proceeding on the petitioner's I l t L
interest. The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. 1 Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the. Board up to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above. Not la'ter than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner,shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each con-tention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration. A ~ petitioner who fails to file such a supplement which satisfies these require-ments with respect to at least one contention will not tie permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave.to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity.to present evidence and cross-examine witnesses. If a hearing-is requested, the Commis'sion will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determina. tion is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment
and make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. - ~ ~ ~ If the final determination is that the amendment involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment. Nomally, the Ccmmission will not issue the amendment until the expiration of the 30-day notice period. However, should circumstances change during the notice feriod such that failure to act in a timely way would resul_t, for example, in derating or shutdown of the facility, the Ccemission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final deter-mination will consider all public and State comments received. Should the' Ccmission take this action, it will publish a' notice of issuan~ce and provide for opportunity -for a nearing after issuance. The Comission expects that the need to take this action will occur very infrequently. A request for a hearing or a petition for leave to intervene must be filed with the' Secretary of the Comission, U. S. Nuclear Regulatory Comission, Washington, D. C. 20555, Attn: Docketing and Service Branch, or may be delivered to the Comission's Public Document Rocm,1717 H Street, N. W., Washington, D. C., by the above date. Wilere petitions are filed during the last ten (10) days of the notice period, it is reouested that the petitioner promptly so inform the Commission by a toli-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identification Number 3737 L__
r o and the following message addressed to Domenic B. Vassallo: petitioner's name and telephone number; date petition was mailed; pl, ant name; and publi-cation date a'nd page number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Executive Legal Director, U. S. Nuclear.- Regulatory Comission, Washington, D. C. 20555, and to H. S. Sanger, Jr., Esquire, General Counsel, Tennessee Valley Authority, 400 Ccmerce Avenue, E11B 33C, Knoxville, Tennessee 37902, attorney for the licensee. Nontimely filings of-petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for, hearing will not be entertained absent a determination by the Cemission, the presiding officer or the Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the' petitioner has made a substantial showing of good cause for the granting of a late petition and/or request. That detemina-tion will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v)and2.714(d), i For further details with respect to this action, see the application for amendment, dated July 13, 1983, as supplemented July 21, 1983, which is available for public inspection at the Comission's Jublic Document Room, 1717 H Street, N. W., Washington, D. C., and at the Athens Public Library, South and Forrest, Athens, Alabama 35611. Dated at Bethesda, Maryland, this 24th day of October,1983. FOR THE NUCLEAR REGULATORY COMMISSION / Domenic B. Vassallo, Chief Operating Reactors Branch 82 Division of Licensing
o t I c})dt! y, UNITED STATES NUCLEAR REGULATORY C0FMISSION TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND PROPOSED NO !!GMIe!CA!!T MAIA?05 CONSIDERATION DETERMIMATION AND OPPORTUMITY FOR HEARING The U. S. Nuclear Regulatory Commission (the Comission) is considering issuance of an amendment.to Facility Operating License No. DPR-33, issued to Tennessee Valley Authority (J;he licensee), for operation of the Browns Ferry Nuclear Power Plant, Unit No. 1, located in Limestone County, Alabama. The amendment would revise the Technical Specifications (T.S.) of the l , operating license to:
- 1). modify the core physics, thermal and hydraulic limits to be consistent with the reanalyses associated with replacing about.
1/3 of the core during the curr'ent refueling ou,tage and 2) reflect plant modifications perfortned during the current refueling and modification outage, which started on April 16, 1983. Specifically, the amendment would result in changes to the T.S. in the following eleven areas: 1) Changes to the license related to the Cycle 6 core reload involving removal of depleted fuel assemblies in about one-third of the nuclear reactor core and replacement with new fuel of the same type previously loaded in the core with attendant license changes in the core pr tection safety limits and reactor protection system setpoints. The actual changes are a slight adjustment (by 0.01 in initial core life) in the Operating l Limit Minimum Critical Power Ratio (OLMCPR), an added table on maximum l average planar linear heat generation rate (ItAPLHGR) versus average planar excosure and a change to the bases for the total relief cacacity of the l safety relief valves. Uff -t3tl40o @ L
1 2 2) Changes to the T.S. to revise the tables listing surveillance instrumentation for suppression pool bulk temperature reelecting the in-stallation of 16 sensors for an improved torus temperature monitoring system and a revision to the basis for the existing limits on torus water temperature; 3) Changes to the T.S. to reflect modifications to the scram discharge volumes (SDV),andtheadditionofasecondscramdischargeinstrument volume (SDIV); each of the SDIVs now have redundant vent and drain valves and new, diverse level instrumentation. The' changes.to the T.S. are to add cperability, surveillance and calibration requirements on the new level instrumentation and valves. 4) Changes to T.S. surveillance instrumentation tables to add new instrumentation for containment high-range radiation monitors and to add new instrumentation, and delete current instrumentation for dyrwell pressure-wide range and suppression chamber wide-range water level in response to requirementsinNUREG-0737,;itemsII.F.1.3,II.F.1.4andIk.F.1.5. 5) T.S. changes to incorporate calibration and surveillance requirements for time delay relays to prevent spurious isolation of..the HPCI and RCIC systems as required by NUREG-0737; item II.K.3.15, 6) Revision of the T.S. table for containment isolation valve surveillance to add two new isolation valves that are p' art of a newly installed redundant cisenarge line from the drywell compressor into containment; 7) Revision of the T.S. to reflect installation of strong backs on personnel airlock doors to allow testing in accordance'with 10 CFR Part 50, Accendix J;
e -. 8) Revision of T.S. to provide limiting conditions for operation and ~ surveillance requirements for electric power monitoring for the reactor protection system power supply; 9) Modify the T.S. to apply to the new analog (continuous measuring) instrumentation. The analog instrumentation replaces certain mechanical-type pressure and level switches with a more accurate and more stable elec-tronic transmitter / electronic switch system and will provide improved performance of trip functions for reactor protection system actuation, and containment isolation. The changes to the T.S. include: a. in the tables on functional' test frequencies, calibration frequencies and surveil' lance ' requirements, for each switch replaced, a'dd the instrument number and type of sensor beneath the parameter being monitored and/or controlled. b. add notes to the above tables to specify how the functional and calibration tests are to be conducted. in addition to the above administrative changes, the calibration c. requirements have been changed to incorporate extended calibration intervals. Hcwever, the required setpoints, functional test fre-quencies and channel check frequencies for the instrumentation will not be changed. The new calibration requirements, together with the new instrumentation, are expected'to provide a more reliable instrumentation system.
- 10) Change the T.S. to reflect the addition of a therral power monitor.
The purpose of this monitor is to have the Average Power Range Monitor ( ApRM) flow biased neutron flux signal respond to the thermal flux rather 6
than the neutron flux in the core by accounting for the,approximately 6-second thermal time constant of the fuel. The specific changes to the ~ T.S. are: a. Add the words " flow biased" in parenthesis to the heading to the heading for the limits on "APRM Flux Scram Trip Settings" to indicate that the settings are reduced according to the equations given in this section when there is less than 100% core flow. b. Thsre is a trip unit-separate from the APRM flow-biased scram at less than 120% instantaneous neutron flux., A new requirement is being added to require that whenever the mode switch is in the run position, the APRM fixed high flux scram trip setting shall be operable and' set at S 120% power. c. The bases for the neutron flux scram are revised to describe the functions of the APRM Flow-Biased High" Flux Scram, Trip Setting and the Fixed High Neutron Flux Scram Trip. d. Since there is new a new trip system, the tables listing the 4 operability requirements and functional test frequencies on the scram instrumentation have to be revised to add this 'new f* instrumentation.
- 11) Administrative changes to the T.S. involving changes to the Table of Contents to reflect. the above license changes, an editorial change and cor-rections to the list of sample valves to be consistent with present plant configuration.
These revisions to the Technical Specifications would be made in . response to the licensee's application dated July 13, 1983, as supplemented July 21, 1983. i -u-
'-S-Before issuance of the proposed license amendment, the Commission will ' have made findings as required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations. The Comission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commi:;sion's regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident pre-vicusly evaluated; or (2) create the possibility of a new or different kind of accident frem any accident previously evaluated; or (3) involve a significant reduction in a margin of. safety. The Commission has 'provided guidance concerning the application of the standards by providing examples,of actions that are likely, and are not likely, to involve significant hazards considerations (48 FR 14870). The first three examples of actions not likely to involve significant hazards considerations are: ~ "(i) A purely administrative change to technical specifications: for example, a chan'ge to achieve consistency throughout the, technical specifi-cations, correction of an error, or 'a change in nomenclature. (ii) A change that constitutes an additional limitation, restriction, or control not presently included in the technical ' specifications: for example, a more stringent surveillance requirement. (iii) For a nuclear power reactor, a change resulting from a nuclear reactor core rel.oading, if no fuel assemblies significantly different from .those found previously acceptable to the NRC for a previous core at the ~
facility in question are involved. This assumes that no significant changes are made to the acceptance criteria for the technical specificitions', ~that the analytical methods used to demonstrate conformance with the technica.1,. specifications and regulations are not significantly changed, and that NRC has previously found such methods acceptable." Each of the eleven changes to the T.S. described previously is encompassed by one of the above examples of actions nbt likely to involve a significant' hazards consideration. The basis for the staff's determination on each of the eleven changes is discussed below. 1. Core Reload The changes to the T.S. associated with removing depleted spent fuel from the reactor and replacing these with new fuel assembl.ies is enecmpassed by example (iii) above of those actions not likely to involve a significant hazards consideration. The proposed reload involves fuel assemblies of the same type as previously found acceptable by the staff and loaded in the core in previous cycles. The analytical methods used by the licensee to demonstrate conform-ance to the technical specifications have been previously approved by the staff. In addition, no changes have been made to the acceptance criteria for the technical specification changes involved. Since the replacement fuel assemblies'are of the same type previously added to all three Browns Ferry units and other BWRs and since the ccdes, nodels and analytical techniques used to analyze the reload have been generically approved by the NRC, the changes to the T.S. associated with the reload are clearly enccmpassed by example (iii) of the guidance provided e
~ by the Comission for an action not likely to involve a significant hazards consideration. 2. Changes Related to-Torus Modifications On January 19,1982, the Commission issued an Order in the matter of Browns Ferry Unit I requiring completion - during the current refueling outage - of the plant modification required by the Mark I program so as to ccmply with the Staff's Acceptance Criteria contained in Appendix A to NUREG-0661. Numerous modifications are being implemented in the Unit 1 torus during the reload 5 cefueling outage as part of the Mark I Containment Program. These redifications are required by NRC to restore the originally intended margins of safety in the containment des ~ign.' Most of-the major internal structural modifications to the torus were completed during the previous refueling outage. These modifications are discussed in Amendment No. 76 to Facility Operating License No. OPR-33 issued September i5, -1981. The modifications being made during this outage will complete the requirements specified in MUREG-0661, " Safety Evaluation Report, Mark I Containment Long-Term' Program." One of the changes to the T.S. is to revise the tables that list the surveillance instrumentation associated with the suppression pool bulk temperature. This modification provides an improved torus temperature monitoring system which consists of 16~ sensors. This will provide a more accurate. indication of-the torus water bulk temperature as required by "UREG-0661 and will replace the suppression chamber water temperature instruments presently listed in the T.S. Another change to the T.S. is to revise the bases for the present limits on temperature of water in the torus. The present bases for -e -e,-- .y. 9- ~ g n m e
suppression pool temperature limits were founded on th.e Humboldt Bay and. Bodega Bay tests. Consistent with the long-term torus integrity program of NUREG-0661 and NUREG-0783, the-bases require change to account for steam mass fluxes through the safety / relief va'lve (S/RV) T-quenchers. The . proposed bases describe assurances of stable and complete condensation of steam discharged through the S/RVs and adequate residual heat removal (RHR) and core spray pump net positive suction head. As noted above, the femmission ordered that the above torus ~ modifications be implemented.' The changes to the T.S,. are necessary admin-istrative follow up actions essential to the implementation of these improvements. The changes to the T.S. place operability and calibration requirements on the new* temperature monitoring system. Since these are new instruments, the surveillance requirements are not presently in the T.S. Thus, adding these restrictions and controls is encompassed by example (ii) provided by the Commissicn. The bases for the suppression pool temperature limits are also being changed to account for steam mass fluxes through the safety relief valve
- T-quencherr. as ~ required by NUREG-0661 and NUREG-0783.
The proposed: bases describe assurances of. stable and complete condensation of steam discharged through the S/RVs and adequate RHR and care spray pump net positive suction. head. The changes are necessary administrative follow up action essential to the implementation of improvements required by the Commission. Modifying these restrictions is encompassed by example (ii) provided by the Commission. 3. Scram Discharge Instrument Volume The SDVs and SDIVs are being modified to address inadequacies. identified by the partial rod insertion event on Browns Ferry Unit 3 in June 1980. One
.'g. of the modifications includes adding another valve in series to the existing drain and vent valves on the SDV and SDIV. Another modification includes ~ adding electronic level switches to initiate a scram on a high level in the SDIV. On June 24, 1983, the Commission issued Orders for the Browns Ferry Nuclear Plant, Units 1 and 3 to install permanent Scram Discharge System modifications during the Cycle 5 outages for Units 1 and 3. (This is the Cycle 5 outage for Unit 1.) The modifications have been previously com-pleted for Unit 2. The Orders included "Model Technical Specifications which are provided as guidance for preparing Technical Specification changes' that will be required to be approved before operation with the modifi' d e system." Both the. modification of the systems and submission of T.S. changes to place operabi'lity and surveillance requirements on the new instruments and valves were required of the licensee to be in compliance ~. with a Comission Order. 'Thus, the changes to'the T.S. are necessary admin-istrative follow up actions essential to the implementation of these improvements. Adding these new restrictions and controls, which othenvise would not be in the T.S., is encompassed by example (ii) of the guidance previded by the' Comission. 4. Accident Monitoring Instrt: mentation Item II.F.1~of NUREG-0737,*" Clarification of TMI Action Plan Requirements," requires all licensees to install five new monitoring systems and to provide onsite sampling / analysis capability for a specified range of radionuclides. For all six categories, NUREG-0737 states: " Changes to technical specifi-cations will be required." During this refueling outage, the licensee has installed: a) a containment high-range monitoring system, b) a drywell 1..
.10 - wide-range pressure monitoring system and c) a suppress. ion chamber wide-range water level monitoring system. These three items were required by NUREG-0737,itemsII.F.1.3,II.F.1.4andII.F.1.5,respectivdy. The changes to the T.S., which track the model T.S. provided to the licensee by the staff, are to add operability and surveillance ' requirements on the new monitoring systems to the T.S. The revisions also dele'te the present drywell pressure and suppression chamber water level instruments since they are being replaced by items b and c above. The changes to the techr.ical specifications,are necessary admin-istrative follow up actions required by the Commission. Adding the new surveillance requirements and controls'is encompassed by example (ii) of the guidance provided by'the Commission. 5. NUREG-0737, Itsm II.K.3.15. TMI Action Plan Item II.K.3.15 requires licensees.of BWRs to modify pipe- ~ break-detection circuitry so that pressure spikes result'ing from high pressure coolant injection (HPCI) and reactor core isolation cooling -(RCIC) initiation will not.cause inadvertent system isolation. The licensee elected to employ the BWR Owners Group modification. whic.h incorporates a three-second time delay relay (TDR) to prevent spurious isolation. In our letter to the licensee of October 13, 1981, we requested the licensee to provide certain analyses and to " propose the appropriate Surveillance Requirements and Limiting Conditions of Operation for the HPCI and RCIC systems which address this item." The safety evaluation was previded by the licensee's letter of December 16, 1981. All of the Browns Ferry units have had a three-second TDR on the HPCI system. During the current outage for Browns Ferry Unit 1, a TDR was added to the RCIC systen. The proposed changes ~*
- ll - to the Technical. Specifications requiring calibration and surveillance of the time delay relays is in accordance with the requirements of NUREG-0737, item II.K.3.15 and the staff's follow up letter. The changes to the T.S. are necessary administrative follow up actions essential to the implementa-tion of these improvements. The addition of requirements in the T.S. for-the operability and surveillance of the new time delay relays clearly -imposes additional limitations and controls not presently included in the. T.S. and is therefore encpmpassed by example (ii) of the guidance provided by the Commission. 6. Redundant Air Sucoly to Drywell During the' current outage, TVA has installed a.second discharge line from the drywell compressor i'nto containment. This line was added to provide ~ the capability for isolation of approximately one-half of the drywell sup ' pression equipment in the case _of a drywell line leak. This air supply will be used to supply two inboard main steam isolation valves (MSIVs), approxi-mately one-half of the main steam relief valves (MSRVs), and approximately one-half of all other air-operated. equipment in the drywell. This will significan'tly reduce the possibility of any one control air pipe break inside containment from requiring immediate shutdown and isolation due to MSIVs, MSRVs, and drywell coolers being inoperable. Since any line penetrating containment requires two isolation valves, the table in the Technical Speci-fications listing the isolation valves that must be periodically tested is being rev.ised to add these two new isolation valves. TVA has concluded that this modification will increase the margin of safety. The changes to the . technical specifications are necessary administrative follow up actions essential to the implementation of this improvement. The two isolatior L
valvesbeingadde'dtotheT.S.arenewval)snotpresentlylistedinthe x T.S. If they were not added to the table of valves to be periodically tested, there would be no T.S. requirement to test these valves. Adding these ad-ditional controls is enccmpassed by example (ii) of the guidance provided - by the Comission. 7. Modification of Airlock Doors Section III.D.2(b) of Appendix J,10 CFR Part 50, requires that air locks shall be tested at 6 month-intervals at an internal pressure not less than P P, is defined as "the calculated peak. containment internal pressure a. relatedtothedesignbasjsaccidentandspecifiedeitherinthetechnical specification or associated bases." Reactor plants designed orior to the issuance of Appendix J o'ften do not have the capability to test airlocks at P without the installation of strongbacks or the performance of mechanical a ~ adjustments to the~ operating mechanisms of the inner doors. The reason for this is that th,e inner doors are designed to seat with hccident pressure on . the containment side of the door, and therefore, the operating mechanisms were not designed to withstand accident pressure in the opposite direction. When the airlock is pressurized for a local airlock test. (i.e., pressurized between the doors), pressure is exerted on the airlock side of the inner door, causing the door to unseat and preventing the performance of a mean-ingful test. The strongback or mechanical' adjustments prevent the unseating of the inner door, allowing the test to proceed. Section 4.7.A.2.g of the present T.S. requires that "the personnel air lock shall be tested at a pressure of' 49.6.psig during each operating cycle." The proposed change to the T.S. is~ to require that "the personnel air lock shall be tested at 6-month intervals at an internal pressure of not less than 49.6 psig." This a
more stringent surveillance requirement is clearly encompassed by example (ii) ofthi guidance provided by the Comission-. 8. Monitorino of RPS_ Power Suoply By letter dated August 7,1978, we advised TVA that during review of Hatch Unit 2, the staff had identifie,d certain deficiencies in the design of the voltage regulator -system of the motor generator sets which supply ~ power to the reactor protection system (RPS). Pursuant to 10 CFR 50.54(f), TVA 'was required to evaluate the RPS power supply for Browns Ferry 1, 2 and 3 in light of the information set forth in our letter. Based on our review of TVA's response, by letter dated September 24, 1980, we informed TVA (and most other BWRs) that "we have detemi'ned that modifications should be per-f.ormed to provide fully' redundant Class IE protection at the interface of non-Class IE power supplies and the RPS." We also advised TVA that "we have found that the conceptual design proposed by the General Electric Company and the ~ installed modification on Hatch are acceptable solutions to our concern." By letter dated December 4,1980, TVA committed to install the required modifications. By letters dated October 30, 1981 and July 28, 1982, we sent TVA model Technical Specifications for el,ectric' power moni-toring of the RPS design modification. During the current outage of Unit 1, the RPS is being modified to provide a fully redundant Class IE protection at the interface of the non-Class IE power supplies and the RPS. This will ensure that failure of a non-Class IE reactor protection power supply will not cause adverse interaction to the Class IE reactor. protection system. The Technical Specifications are being revised similar to the model T.S. provided to TVA to reflect the limiting conditions for operation and surveillance requirements associated with the RPS modifications. Page 42
O. is being modified to add a description o.f these sections in the bases. The changes to the T.S. are necessary administrative fol. low up actions essential to the implementation of these improvemen'ts. The additional limi-tations and' controls, which are presently not in the T.S., are encompassed by example (ii).of the guidance provided by the Commission. 9. Analec Trip' System The RPS, the primary containment isolation system (PCIS), and the core standby cool'ing systems (CSCS) use mechanical-type switches in the sensors that monitor plant process parameters. These mechanical-type switches are very subject to drift in the set-point as is evident from the many licensee event reports (LERs) that have been submitted reporting calibration drifts in these switches. Advances in technology make it possible to replace the mechanical- ~ type switches with a more accurate and more stable electronic transmitter / electronic switch system. For several years, TVA has been planning to replace existiny pressure switches that sense drywell and reactor pressures with analog loops and modify the reactor water level indication loops to improve the reliability, accuracy and response time of this instrumentation. The modification involves removing one device and substituting other devices to perform the same function. Changes in design bases, protective function, redundancy, trip point.and logic are not involved. Similar modifications have been approved for other SWRs. As described previously, most of the changes to the T.S. are administrative in nature (i,.e., adding the specific number and types of sensor and adding notes to describe how testing is con-ducted). As such, they are enccccassed by example (i) of the guidance provided by the Conunission. The changes in surveillance reoufrements b
- relate to example (ii) of the guidance provided by the Commissicn.
Some of the surveillance intervals have b6en decreased as appropriate for each new instrument. However, the overall effect of the changes in technical specifications will be to increase the total surveillance requirements in ~ support of a more reliable instrumentation system. 10. Thermal Power Monitor During this outage, the licensee is installing a flow-biased simulated thermal power monitor. These monitors are installed on most all BWRs; the justification for these monitors is discussed in the " Bases" for the APRM settings in the BWR Standard Technical Specifications, NUREG-0123 (BWR/4, STS, Section 2.2.1, page 82-7). 'The monitors are installed to have the APRM flow-biased neutron' flux signal respond to the themal flux rather than the neutron flux by accounting for the approximately 6-second thermal ~ time constant of the fuel. The addition of the themal power monitor will prevent a flow-biased neutron flux scram when a transieht-induced neutron flux spike occurs that is a short time duration and does not result in an instantaneous heat flux in excess of transient limits. Neutron flux is damped by approximately a 6-second fuel time constant.,Jhis featurr. will reduce the number of scrams due to small fast flux transients such as those which result from control valve and MSIV testing and small perturbations in water leyel and pressure. A thermal power monitor was installed in Browns Ferry L' nit 2 during the last outage and approved by Amendment No. 85 to Facility Operating License No. DPR-52 issued March 11, 1983. As identified previously, the changes to the T.S. are to add operability and functional test frequency requirements for this new trio
. 4 system and to add a description of this new trip system,in the " Bases." The changes to the T.S. are necessary administrative follow up actions essential to the implementation of these improvements. The additional limitations, restrictions and controls, which are not presently included in the T.S., are encompassed by example (ii) of the guidance provided by the Commission. 11._ Administrative Changes Several administrative changes are being made to the Technical . Specifications. These include revising the Table of Contents to reflect the changes discussed above, an editorial change and corrections to the list of sample valves to reflect the corrent plant configuration. These changes are editorial in* nature and have no safety significance. These changes are encompassed by example (i) cited by the Comission as an action ( not likely to pose a significant hazards consid'eration. Since all of the changes to the T.S. are encompassed by an example.in the guidance provided by the Comission of actions not likely to involve a significant hazards consideration, the staff has made a proposed determina-tion that the application for amendment involves no signific3nt hazards consideration. The Comission is seeking public coments on this proposed determination. Any. coments received within 30 days after 'the date of
- ublication of this notice will be considered in making any final determi-nation.
The Comission will not normally make a final determination unless it receives a request for a hearing. .=+w-, -. ~.. -
Comments should be addressed to the Secretary of the Commission, U. S. Nuclear Regulatory Commission, Washington, D. C. 20555, Attn: Docketiig~andServiceBranch. By November 28, 1983, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding , and who wishes to participate as a party in the proceeding must file a written petition for leave,to intervene. Request for a hearing and peti-tions for leave to intervene shall be filed in accordance with the Cermission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. If a request for a hearing or petition for leave to inter-vene is filed ~by the above date, the Commission or an Atomic Safety and Licensing Board, designated by.the Commission or by the Chairman of the ~. Atomic Safety and Licensing Board Panel, will r'ule on the request and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order. As required by 10 CFR 52.714, a petition for leave to intervene shall set forth with particuiarity the interest of the petitio,ner in the proceed-ing, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to 'the following factors: (1) the nature of the petitioner's right under the Act to be mace a party to the. proceeding; (2) the nature and extent of the petitioner's property,, financial, or other interest in the proceeding; and (3) the possible effect cf any order which may be entered in the proceeding on the petitioner's + e
interest. The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the~ Board up to fifteen (15) days ' prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above. Not la'ter than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner,shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each con- ~ tention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of.the amendment under consideration. A ~ petitioner who fails to file such a supplement wh.ich satisfies these require-ments with respect to at least one contention will not 'b'e permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity.to present evidence and cross-examine witnesses. If a hearing is requested, the Commis'sfon will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment ~j
~ 19 and make it effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. - ~ ' - If the final determination is that the amendment involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment. Normally, the Ccmission will not issue the amendment until the expiration of the 30-day notice period. However, should circumstances change during the notice feriod such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Ccmmission may issue the license amendment before the expiration of the 30-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final deter-mination will consider all public and State comments received. Should the ~ Ccmission take this action, it will publish a notice of issuance and provide for opportunity for a hearing after issuance. The Comission expects that the need to take this action will occur very infrequently. A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U.. S. Nuclear Regulatory Comission, Washington, D. C. 20555, Attn: Docketing and Service Branch, or may be delivered to the Comission's Public Document Roem,1717 H Street, N. W., Washington, D. C., by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is reouested that the petitioner promptly so inform the Comission by a toli-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identification Number 3737 i l l l
and the following message addressed to Domenic B. Vassello: petitioner's name and telephone number; date petition was mailed; pl, ant name; and publi-cation date and page number of this FEDERAL REGISTER notice. A copy of the petition should also be sen*. to the Executive Legal Director, U. S. Nuclear. Regulatory Comission, Washington, D. C. 20555, and to H. S. Sanger, Jr., Esquire, General Counsel, Tennessee Valley Authority, 400 Ccmerce Avenue, E11B 33C, Knoxville, Tennessee 37902, attorney for the licensee. Nontir6ely filings of-petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for, hearing will.not be entertained absent a determination by the Comission, the presiding officer or the Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the' petitioner has made a substantial showing of good e cause for the granting of a late petition and/or request. That detennina-tion will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v)and2.714(d). i For further details with respect td this action, see the application for amendment, dated July 13, 1983, as supplemented July 21, 1983, which is available for public inspection at the Comission's Jublic Document Room, 1717 H Street, N. W., Washington,-D. C., and at the Athens Public Library, South and Forrest, Athens, Alabama 35611. Dated at Bethesda, Maryland, this 24th day of October,1983. FOR THE NUCLEAR REGULATORY COMMISSION / Domenic B. Vassallo, Chief Operating Reactors Branch e2 Division of Licensing ...- ~
i l \\ 7590-01 f pr/ 4 UNITED STATES NUCLEAR REGULATORY COMMISSION TENNESbEEVALLEYTUTHCRITY DOCKET NOS. 50-259, 50-260, 50-296 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENCMENTS TO FACILITY OPERATING LICENSES AND OPPORTUNITY FOR PRIOR HEARING The U. S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to Facility Operating Licenses No. DPR-33, DPR-52 and DPR-68, issued to Tennessee' Valley Authority (the licensee), for operation of the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3 located in Limestone County, Alabama. The acendments would revise the Technical Spe'i#ications of the operatinc c licenses to aermit reactor operation at power levels of 50% of rated power with one recirculation loop out of service. Presently, the Browns Ferry Nuclear Power Plant, Units 1, 2 and 3 Technical Specifications (TSs) recuire plant shutdown if an idle recirculation loop cannot be returned to service within 24. hours. The change proposed by the licensee would delete this TS requirement and modify the TSs to provide for: appropriate Average Power - Range Monitor (APRM) flux scram trip and rod block settihgs; an increase in the safety limit Minimum Critical Power Ratio (MCPR) value; revisions to the allowable Average Planar Linear Heat Generation R. ate ( APLHGR) values suitable for use with an idle recirculation 1000; and the inclusion of APRM flux and core plate pressure drop limits during single loop operation; in accordance with the licensee's application for amendments dated March 4, 1982 as modified by September 3,1983 and January 6,1983 submittals. n -pp+k$W:T~
\\, Prior to issuance of the proposed license amendments, the Commission will have rade findings recuired by the Atomic Energy Act of 1954, as arended (the Act) and the Conmission's regulations. By February 23, 1984, the licensee may file a reouest for a hearing with respect to issuance of the amendments to the subject facility operating Itcenses and any persnn whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for leave to intervene. Request for a hearing and petitions for leave to intervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. If a recuest 'nr a hearing or petition for leave to intervene is filed by the above date, the Cemnission or an Atomic Safety and Licensing Board, designated by the Comission or by the Chairman of the Atomic Safety and Licensing Board Panel', will rule 'on the reouest and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearino or an appro-priate order. As. recuired.by 10 CFR 4?.714, a petition 4r leave to interven'e shall' ~ set forth with particularity the interest of the cetiti$ner in the oraceeding, and how that interest may be affected by the results of the prnceeding. The cetition should specifically exclain the reasons why intervention should be permitted with carticular referexe to the 'ollnwing factors: (1) the nature of the cetitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect o# any order which may be entered in the proceedinn on the petitioner's interest. The petition
should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any-person wno has fileo a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up'to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above. Not later than fifteen (15) days prior to the first prehearing conference ' scheduled in the preceeding, a petitioner shall file a supplem,ent to the petition to intervene which must include a list of the cdntentions which are sought .to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters withig the scope of the amendment under censideration. A petitioner who fails to file such a supplement which satisfies these 'equirements with respect to r at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, anc' have the - opportunity to participate fully in the conduct of the iearing, including the opportunity to present evidence and cross-examine witnesses. A request for a hearing or a petition for leave to intervene shall be filed with the Secretary of the Comnission. U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch, or may be delivered to the Commission's Public Document Rocm, 1717 H Street, N.W. O e
,s a A 4-4 Washington, D.C.,-by the above da.tt. Where ottitions are filed during the last ten (10) days of the notice period, it is reouested that the petitioner er representative for the petitioner prcmptly so inform the Comission by a 'oll-free telephone call to Western Union at IA001 325-6000 lin Missouri (800) l 342-6700). The Western Union operator should be given Dataoram Identification Number 3737 and the following message addressed to Ocmenic B. Vassallo: (petitioner',s name and telephone number); (date petition was mailed); (plant. ~ name); and (publication date and page number of this FEDERAL REGISTER notice)s A copy of the petition should also be sent to the Exec'utive Leoal Director, U.S. Nuclear Regulatory Co$nission, Washington, D.C. 20555, and to Mr. H. S.. . Sanger, Jr., Esquire, General Counsel, Tennessee Valley Authority, 400 Comerce Avenue, E 11B 33C, Knoxville, Tennessee 37902. ./ Ncntimely filings of petitions for leave to intervene, amended petition's, supplemental petitions and/or reouests for hearing will not be entertained absent a determination by the Comission, the presiding officer or the Atomic Safety and Licensino Board designated to rule on the petition and/or request, that the petitinn and/or request should be granted based upon a balancing of. ~ .thefactorsspecifiedin10CFR2.714(a)(1)(i)-(v)andE.714(d). For further details with resoect to this action, see the apolication for arrendments dated March 4,1982 as modif.ied by Septemner 3,1982 and l l = l m
s 4. January 6,1983 submittals, which is available for public inspection at the Comission's Public -Document Room,1717 H Street, N.W.. ' Washington, D.C., and at the Athens Public Library, South and Forrest, Athens, Alabaca 25611. Dated at Bethesda, !!aryland this 16th day of January,1984. FOR THE-NUCLEAR. REGULATORY COMf1ISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division o,f Licensing t e 4 e O O 6 r O e 0 e
a,., a UNITED STATES NUCLEAR REGULATORY COMMISSION 4 DOCKdTNO.50-317 41 BALTIM0REGASINDELECTRICCOMPANY [$ if &l* NOTICE OF CONSIDERATION OF !$$UANCE OF AMENOMENT TO /" FACILITY OPERATING LICENSE AND OPPORTUNITY FOR PRIOR HEARING The United States Nuclear Regulatory Commission (the Consission) is considering issuance of an amendment to Facility Operating License No. OP1-53 issued to Baltimore Gas and Electric Company (the licensee), for operation of the Calvert Cliffs Nuclear Power Plant, Unit No. I located in Calvert County, Maryland. The amendment would revise the Limiting Conditions for Operation and Surveillance Requirements for containment tendons as contained in the Appendix A Technical Specifications for Calvert Cliffs Unit No.1 in accordance with the licensee's application dated. March 7,1983. The pro-posed changes in the Technical Specifications include a provision to allow normalization of tendon lift-off forces in determing continued containment tendon integrity. In addition, a 90 day period would now be permitte'd to ~~ investigate eyidence of possible abnormal degradation of the tendon system. Prior to issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations. By July 18, 1983 the licensee or a petitioner may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this pro-caeding and who wishes to participate as a party in the proceeding must file a written petition for leave to intervene. Requests for a hearing and petitions " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. 4 W f-2,4 0Mb. N Y f
a 7590 01 2-If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or an Atomic Safety and Licensing Board, designated by the Comission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order. As required by 10 CFR 52.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors: (1) the nature of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's tnterest. The petition ~ should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. ~Any person who has filed a petition for leave to intervene or who has been admitted as a party may amend the petition without requesting leave of the Board up to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements de-scribed above. No later than fifteen (15) days prior to the first-prehearing, conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set
O, t 7590-01 . forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration. A petitioner who fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be pemitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitat, ions in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the opportunity to present evidence and cross-examine witnesses. A request for a hearing or a petition for leave to intervene shall be filed with the Secretary of the Commission, United States Nuclear Regulatory Commission, Washington, D. C. 20555, Attention: Docketing and Service Branch, or may be delivered to the. Commission's Public Document Room,1717 H Street, N. W., Washington, D. C. by the above date. Where petitions are filed during the last ten (10) days of the notice
- period, it is requested that the petitioner or representative for the petitioner promptly so inform the Commission by a toll-free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following message addressed to Robert A. Clark: (petitioner's name and telephone number), (date petition was mailed); (plant name), and (publication date and page number of this FEDERAL REGISTER notice). A copy of the petition should also be sent to the Executive legal Director, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, and to James A. Biddison, Jr., General Counsel, G and E Building, Charles Center, Baltimore, Maryland 21203, attorney for the licensee. Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will no.t be entertained
e 7590-01 4-absent a determination by the Commission, the presiding officer or the Atomic Safety and Licensing Board designated to rule on the petition and/or request. That determination will be based upon a balancing of the factors specified in 10 CFR 32.714(a)(1)(i)-(v) and 32.714(d). For further details with respect to this action, see the application for amendment dated March 7,1983, which is available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.* C., and at the Calvert County Library, Prince Frederick, Maryland. Dated at Bethesda, Maryland this 7th day of June,1983. FOR THE NUCLEAR REGULATORY COMMISSION n D-obert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
j e, ' s 7590-01 4 ~ 0 M 3 f, I 4'f UNITED STATES NUCLEAR REGULATORY C009t!S$!0N q 4ll"l-BALTIMDRE GAS AND ELECTRIC COMPANY f DOCKET N05. 50-317 AND 50-318 NOTICE OF CONSIDERATION OF ISSUANCE OF AMEN 0MENTS 70 FACILITY OPERATING LICENSES AND OPPORTUNITY FOR PRIOR HEARING 1 i The U. S. Nuclear Regulatory Comunission (the Ceaunission) is considering issuance of amendments to Facility Operating License Nos. DPR-53 and DPR-69, issued to Baltimore Gas and Electric Company (the. licensee), for operation of the Calvert Cliffs Units 1 and 2 located in Calvert County, Maryland. The amendments would revise the provisions in the Technical Specifications i (TS) relating to the operability of the air recirculation and cooling units. 1 The proposed revision to TS 3.6.2.2, " Containment Cooling System," would allow consideration of the operability status of the containment spray system in detemining remedial action should elements of the air recirculation and cooling units become inoperable. The proposed revision to TS 3.6.2.2 is in accordance with the licensee's application for amendment dated September 30, 1983 as supplemented by letter dated January 18, 1984. Prior to issuance of the proposed license amendments, the Comunission will have made findings required by the Atomic Energy Act of 1954, as amended (the I 4 Act), and the Comunission's regulations. i 4 By May 17, 1984 , the licensee may file a request for a hearing with r respect to issuance of the asiendments to the sub.iect facility operating Itcenses i and any person whose interest may be affected by this proceeding and who wishes i i to participate as a party in the proceeding must file a written petition for I 1 ~-
t i , leave to intervene. Request for a hearing and petitions for leave to in-tervene shall be filed in accordance with the Commission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. If a reouest for a hearing or petition for leave to intervene is filed by the above date, the Comission or an Atomic Safety and Licensing Board, designated by the Com-mission or by the Chainnan of the Atomic Safety and Licensing Board Panel, will rule on the reouest and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice,0f hearing or an appro-priate order. As recuired by 10 CFR 62.714, a petition for leave to intervene shall *
- et forth with particularity the interest of the petitioner in the proceeding and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following factors:
(1) the nature of the cetitioner's right under the Act to be made r party to the proceeding; (25 the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered in the proceeding on the petitioner's interest. The petition should also identify the specific aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has 'iled a cetition for leave to intervene or who has been admitted as a party acand the cetition without requesting leave of the Board up to fifteen may I!!' davs artor to the first prehearing conference scheduled in the proceeding, but suc* ar amended Detition must satisfy the specificity requirements described
- 10cVe,
3 Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendments under consideration. A petitioner who fails to file such a supplement which satisfies these requireme,nts with respect to at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding, sub.iect to any limitations in the order granting leave to intervene, and have the opportuni.ty to participate fully in the conduct of the hearing, including the occortunity to present evidence and cross-examine witnesses. A reouest for a hearing or a petition for leave to intervene must be filer 4 with the Secretary of the Comission, U.S. Nuclear Regulatory Com-mission, Washington, D.C. 20555, Attention: Docketing and Service Branch, or may be delivered to the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that the peti-tiener or representative of the petitioner promptly so inform the Commission by a toll free telephone call to Western Union at (800) 325-6000 (in Missouri (800) 342-6700). The Western Union operator should be given Datagram Identi-
- ' cation Number 3737 and the following message addressed to James R. Miller:
(cetf *.4crer's name and telephone number), Idate petition was mailed),(plant name),
4 and (publication date and page number of this FEDERAL REGISTER notice). A copy of the petition should also be sent to the Executive Legal Director, U.S. Nuclear Regulatory Comission Washington, O.C. 20555, and to James A. Biddison, Jr., General Counse!, G and E Building Charles Center, Baltimore, Maryland 21203, attorney for the licensee. ' Nontimely filings of petitions for leave to intervene, amende'd petitions, supplemental petitions and/or reouests for haaring wil1 not be entertained absent a determination by the Coteission, the presiding officer or the Atomic Safety and Licensing Scard desiar.ated to rule en the' petition and/or request. That detemination will 'be based upon a balancin'g of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d). For further detafis with respect to this action, see the application for amendrients dated September 20, 1983'and th'e licensee's letter dated January 18, 1984 which are available for pubife inspection at the Comis-sion's Public Document Room,1717 H Street, N.W., Wshington, D.C., and at G the Calvert County Library, Prince Frederick, har viand. Dated at Bethesda, Maryland this.6th day of April,1984. FORTHENUCLEARECGULATORYCOMMISSION k m s',. James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing l r [
f i.,- 7590-01 q6 Of SI UNITED STATES NUCLEAR REGULATORY ~C0fMISSION BALTIMORE GAS ANU ELECTRIC COMPANY I DOCKET NO. 50-318 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE AND OPPORTUNITY FOR PRIOR HEARING I The U. S. Nuclear Regulatory Connission (the Cosmission) is considering issuance of an amendment to Facility Operating License No. DPR-69, issued to [ Baltimore Gas and Electric Company (the licensee), for operation of the Calvert Cliffs Nuclear Power Plant, Unit No. 2, located in Calvert County, Maryland. The amendment wuld revise the pmvisions in the Technical Specifica-tions(TS)relatingtotheoperability.andsurveillancefortheauxiliary ) feedwater system. The proposed rev'ision to TS 3/4.7.1.2, " Auxiliary Feedwater System" includes a provision to extend the maximum period of inoperability of an auxiliary feedwater pump from 72 hours to 7 days. The proposed change to TS 3/4.7.1.2 is in accordance with the licensee's application for amendment dated April 9,1984, as supplemented by a letter dated May 4,198,4. Prior to issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Counission's regulations. t 4 4 'y. f0 l +4#52401M L
t.
- By
, the licensee may file a request for a hearing with respect to issuance of the amendment to the subiect facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written petition for leave to intervene. Request for a hearing and petitions for leave to intervene shall be filed in accordance with. the Comission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2. If a request for a hearing or petition for leave to intervene is filed by the above date, the Comission or an Atomic Safety and Licensing Board, designated by the Comission or by the Chairman of the Atomic Safety and Licensing Board Panel, will-rule on the request and/or petition and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appro-priate order. As required by 10 CFR 62.714, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceedino, and hcw that interest may be affected by the results of the proceeding. The oeFtion should specifically explain the reasons why intervention should be oemitted with particular reference to the following factors: (1) the nature of the cetiticner's right under the Act to be made a party to the proceeding; (2) the cature and extent of the petitioner's property, financial, or other l interest in the proceeding; and (3) the possible effect of any order which r.av ba entered in the proceeding on the petitioner's interest. The petition 1 seculd also ioentify the specific aspect (s) of the subject matter of the { rreceedirg as to which petitioner wishes to intervene. Any person who has C ar ! re* -inn for leave to intervene or who has been acmitted as a party b_ _
t -.\\ nay amend the petition without reouesting leave of the Board up to fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above. Not later than fifteen (15) days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter, and the bases for each contention set forth with reasonable specificity. Contentions shall be limited to matters within the scope of the amendment under consideration. A petitioner wh'o fails to file such a supplement which satisfies these requirements with respect to at least one contention will not be permitted to participate as a party. Those pemitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opoortunity to participate fully in the conduct of,the hearing, including the opportunity to present evidence and cross-examine witnesses. A reouest for a hearing or a petition for leave to intervene must be
- iled with the Secretary of the Comission, U.S. Nuclear Regulatory Com-mirsion, Washington, D.C.
20555, Attention: Docketing and Service Branch, or may be delivered to the Commission's Public Document Room, 1717 H Street, N.W. Washington, D.C., by the above date. Where petitions are filed during the last ten (10) days of the notice period, it is requested that the cet:ttoner orcrotly so inform the Comission by a toll-free telephone call te 'testeer l'nion at (800) 325-6000 (in Missouri (800) 342-6700). The Wste '.'aicr coerator should be given Datagram Identification Number 3737 . J. -
o -4 and the following message addressed to James R. Miller: (petitioner'sname and telephone number), (date petition was mailed), (plant name), and (publica-tion date and page number of this FEDERAL REGISTER notice). A copy of the petition should also be sent to the Executive Legal Direct'or, U.S. Nuclear-Regulatory Comission, Washington, D.C. 20555, and to James A. Biddison, Jr., General ' Counsel, G and E Building, Charles Center, Baltimore, Maryland 21203, attorney for the licensee. Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a detemination by the Comission, the presiding officer or the Atomic Safety and Licensing Board designated to rule on the petition and/or request, that the petitioner has made a substantial showing of good cause for the granting of a late petition and/or request. That datermination will be based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d). For further details with respect to this action, see the application for amendment dated April 9,1984, and a supplement dated May 4,1984, which are available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Calvert County Library, Prince Frederick, Maryland. Dated at Bethesda, Maryland this 1st day of May,1984. FOR THE NUCLEAR REGULATORY COMMISSION _ 5.Y
- 2. /
b James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing ..}}