ML20215H785
| ML20215H785 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/22/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 8705070049 | |
| Download: ML20215H785 (35) | |
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DISTRIBUTION w/o encl wmDocketJHe;is/ encl ^
NRCPDR w/enci April 22, 1987 CV0gan HAbelson DOCKETN0(S). 50-333 See Attached list of Addressees
SUBJECT:
POWER AUTHORITY OF THE STATE OF NEW YORK James A. Fitzpartick NuclearPower Plant
( The following documents conceming our review of the subject facility are transmitted for
! your infonnation.
Notice of Receipt of Application, dated .
Draft / Final Environmental Statement, dated .
Notice of Availability of Draft / Final Environmental Statement, dated .
Safety Evaluation Report, or Supplement No. dated .
! Environmental Assessment and Finding of No Significant Impact, dated .
O Notice of Consideration of Issuance of Facility Operating License or Amendment to Facility Operating License, dated .
l C Bi-Weekly Notice; Applications and Amendments to Operating Licenses Involving No i Significant Hazards Considerations, dated [see page(s)] .
Exemption, dated .
Construction Permit No. CPPR- , Amendment No. dated .
Facility Operating License No. , Amendment No, dated .
O Order Extending Construction Completion Date, dated .
l Monthly Operating Report for transmitted by letter dated .
I C Annual / Semi-Annual Report-l transmitted by letter dated .
vt l
X OTHER: Bi-Weekly Notice covering period through April 22, 1987. Expiration date for hearing requests and comments; May 22, 1987.
Office of Nuclear Reactor Regulation i
Enclosures:
As stated cc: See next page 3
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esdisy, April 22.1987 /.Nstices . 18331
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I as.weekiy notice: Appacetione and Amendmente to Operating Uconese kwoMng No signifloent Hasarde considerations
. g, . _ _m. 2 Pursuant to Public Law'(P.L)97-415 the Nuclear Regulat Coaunission (the Commission)is puldi. this regular bi-weekly notice.Public Law 97-415 revised section les of the Atomic Energy Act of1954, as amended (the Act) to require the Commission to publish notice of any amendments issued, or proposed to be issued.under a ne w provision of section too of the Act.This provision gra sts the Commission the authority to issue and raske immediately effective any amendment to an operating license upon a determination by the Commiselon that such amendment involves no significant hazards consideration. notwithstanding the pendency before the Commission of a request for a hearing from any person.
This bi-weekly notice includes all amendments issued, or proposed to be issued. since the date of publication of the last bi-weekly notice which was i published on April 3.1987 (52 FR 11352) through April 10.1987.
MA=etion of issummes of Amead==t to Facility Operating 11=a= and Proposed No Significant Hazards Consideration Determination and Opportunity for Headag 8
%e Commiselon has made a proposed determination that the following amendment requests involve no significant hasards consideration. Under the Commission's regulations in 10 CPR 50.92. this means that operation of the facility in accordance with the proposed amendments would not (1) involve a significant increase in the probability or
)
1 consequences of an accident previously 1
13332 Federal Register / Vcl. 52, No. 77 / W:dnesday April 22. 1987 / Notices.
evaluated, or (2) create the possibility of following factors:(1) The nature of the to act in a timely way would result for o new or different kind of accident from petitioner's right under the Act to be example. in derating or shutdown of the any accident previously evaluated; or (3) made a party to the proceeding: (2) the facility, the Comminion may issue the involve a significant reduction in e nature and extent of the petitioner's license amendment before the margin of safety.ne basis for this property, financial, or other interest in expiration of the 30-day notice period, proposed determination for each the proceeding: and (3) the possible provided that its fmal determination is amendment request is shown below. effect of any order which may be that the amendment involves no The Commission la seeking public entered in the proceeding on the significant hazards consideration. The comments on tlus proposed - petitioner's interest. ne petition should final determination will consider all determinaticn. Any comments received also identify the specific aspect (s) of the public and State comments received within 30 days after the date of sub)ect matter of the proceeding as t publication of this notice will be before action is taken. Should the which petitioner wishes to intervene. Commission take this action,it will considered in making any final Any person who has filed a petition for determination. The Comminion will not leave to intervene or who has been publish a notice of iuuance and provide normally make a final determination admitted as a party may amend the I r opportunity for a hearing after unless it receives a request for a petition without requesting leave of the issuance. The Commission expects that hearing. Board up to fifteen (15) days prior to the the need to take this action will occur Written comments may be submitted first prehearing conference scheduled in very infrequently.
by mail to the Rulas and Procedures the proceeding. but such an amended A request for a hearing or a petition .
Branch, Division of Rules and Records, petition must satisfy the specificity for leave to latervene must be filed with Office of Administration. U.S. Nuclear requirements desoibed above. the Secretary of the Commission. U.S.
Regulatory Commission. Washington, Not later than fifteen (15) days prior to Nuclear Regulatory Commission.
DC 20655, and should cite the the firet prehearing conference Washington. DC 20555. Attentiore publication date and page number of scheduled in the proceeding, a petitioner Docketing and Service Branch. or may this Federal Register notice. Written shall file a anpplement to the petition to be delivered to the Commission's Public comments may also be deitvered to intervene which must include a het of Document Room,1717 H Street. NW.,
Room 4000, Maryland National Bank - the contentions which are sought to be Washington. DC, by the above dnte.
Bui 7735 Old Georgetown Road, Btigated in the matter, and the bases for Where petitions are filed during the last Be Maryland from til a.m. to each contention set forth with 520 p.m. Copies of written comasents reasonable specificity. Contentions shall ten (to) days of the notice period. It is received may be examined at the NRC be liraited to matters within the scope of requested that the petitioner promptly so Public Document Room.1717 H Street the amendment under consideration. A infonn the Comrniuipn by a toh
. NW, Washington. DC.The 8111ag of petitioner who fails to file such a telephone call to Western Union at (800) requests for hearing and pe6 .ns for supplement which satisfies these 325-6000 (in Missouri (800) 342-6700).
leave to intervene is discueeed below. requirements with respect to at least one The Western Union operator should be By june 5,1987, the licensee may file a contention will not be permitted to given Datagram identification Number request for a hearing with rupect to participate as a party. 3737 and the following message issuance of the amendment to the %ose permitted to intervene become addressed to (Project Directorf.
subject facili operating bcense and parties to the proceeding. sub)ect to any Petitioner's name and telephone ,
any person w interest may be limitations in the order granting leave to number; date petition was mailed; plant '
cffected by this proceeding and who intervene, and have the opportunity to name; and publication date and page wishes to participale as a party in the participate fully in the conduct of the number of this Federal Register notice.
I proceeding most file a written petition bearing, includmg the opportunity to A copy of the petition should also be for leave to intervene. Requests for a present evidence and cross-examine sent to the Office of the General hearing and petitions for leeve to witnesses. Counsel-Bethesda, U.S. Nuclear intervene shall be filed in accordance !! a hearing is requested, the Regulatory Commission. Washington, with the Commission's " Rales of Commission will make a final DC 20555, and to the attorney for the Practice for Domestic Ucensing determination on the issue of no gIC'"*"
Proceedings"in 10 CFR Part 2. If a significant har.ards consideration.He 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 la that the supplemental petitions and/or requests Safety and Ucensing Board, designated amendment request involves no 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 may issue the amendment Commission, the presiding officer or the Board Panel, will rule on the request and make it immediately effective, presiding Atomic Safety and Ucensing and/or petition and the Secretary or the notwithstanding the request for a Board, that the petition and/or request
- designated Atomic Safety and Ucensing hearingcAny hearing held would take should be granted based upon a Board willissue a notice of hearing or place afterissuance of the amendment. balancing of factors specified in to CFR an appropriate order. If the final determination is that the 2.714(s)(1)(1) through (v) and 2.714(d).
- As required by to Cl3 2.714, a amendment involves a significant For further details with respect to this petition for leave to intervene shall set hazards consideration, any hearing held action, see the application for forth with particularity the interest of would take place before the issuance of amendment which is available for public the petitioner in the proceeding, and any amendment.
Normally, the Commission will not inspection at the Commission's Public how that interest may be affected by the nt Romn, W H ht. W, resuhe of tne proceeding.The petition *
. lssue the amendment until the .
should specifically explain the reasons. ; . expiration of the 30-day notice period. Washington,. DC, and at the local pubh,c wh intervention should be permitted - However, should circumstances change document room for the particular facility with particular reference to the during the notice period such that failure involved.
Federal Register / Vol. 52, No. 77 / W:dn:sday, April 22. 1987 / N:tices 13333 Arkansas Power and ught Co., Docket Changes identified above that are Robinson Steam Electric plant. Unit No.
No.56-313, Arkansas Nuclear One, Unit ,,, quested to correct errors which 2, to reflect organlaation changes.
No.1. Pope County, AR occurred only in the licensee's Basis forproposedno significont Date ofomendment request: duplication process are not being hozords considemtion determination:
December 12.1986. considered by the Commission. The The Commission has provided Description ofomendment request: official Commission record is correct standards for determining whether a The amendment request identifies five and therefore no changes are necessary, significant hazards consideration exists proposed changes in the Arkansas Basisforproposedno signift' cont (10 CFR 50.92(c)). A proposed Nuclear One. Unit 1. Technical horoids considemtion determination: amendment to an operating license for a Specifications as follows: The Commission's staff has reviewed facility involves no significant hazards 1, Change Table 4.1-3 at item 1.c to the licensee's no significant hazards cons!Jeration if operation of the facility delete the reference to footnote (11) and consideration determinations and spees in accordance with the proposed to delete the footnote itself. The item with the licensee e analyses. All of tne proposed changes are to remove amendment would not (1) involve a and the footnote relate to a requirement significant increase in the probability or applicable from da e of license through ambiguities, remove outdated . .
consequences of an accident previously Cycle 2 only and therefore are no longer mquirements, correct misspelled words, evalucted:(2) create the possibility of a applicable provide consistency within the Technical Specifications or to provide new or different kind of accident from
. 2. Change Table 4.1-3 to delete item 7 any accident previously evaluated; or (3) and associated footnote: change for administrative and organizational changes. involve a significant reduction in a Specification 3.3.1 to replace paragraph The Commission has provided margin of safety.
- (G) with paragraph (G) as noted in this specification and delete the associated guidance concerning the application of Carolina Power and ught Company footnote; and change Specification 3.3.4 the standards in 10 CFR 50.92 by has reviewed their proposed change in to replace paragraphs *(B) and *(C) as providing certain examples in 51 FR accordance with to CFR 50.92(c) and noted in this specification and delete the 7750. An example of actions involving has determined that the proposed associated footnote. The changes relate no significant hazards considerations is change does not:
to the requirements associated with the Example (i), an amendment involving a (1) Involve a significant increase in sodium thiosulfate system which was purely administrative change to the probability or consequences of an removed from service as authorized by a Jechnical specifications: for example, a accident previously evaluated because previous amendment to the license.c change to achieve consistency the amendment changes the
- 3. Change Figure 6.2-1. Management , thro 4hout the technical specifications, organisational structure to reflect Organization Chart, and Figure 612. correction of an error, or a change in organizational changes due to Functional Organization for Plant nomenclature. The proposed Technical promotions and reorganisation without Operations, to reflect a reorganization of Specification modifications correct any reduction in the level of certain positions within the generation, typographical errors, provide managementoversight of activitus transmission and engineering operations consistency withir the Technical affecting plant safety. Furthermore, the of Arkansas power and ught Cen.pany. Specifications and provide for -
redundant addition of a requirement for
- 4. Change 9pecification s.8.2 to correct administrative changes. The propoed PNSC review to Section 8.5.1.6.8 a misspelled word; add page numbers to changes fall within this example.
pages 80. 61 and 86c which apparently - Therefore, since the application for Provides further assurance that such were missing as a result of the licensee's amendment involves proposed changes reviews will be appropriately carried duplication process; correct a misspelled that are similar to an example for which out.
word in Specification 4.4.1.1.2.a; correct no significant hazards considerations (2) Create the possibility of a new or designation "NRC" for "AEC"in exist, the Commission has made a different kind of accident than Specification 4.4.1.1.2.d; change proposed determination that the previously evaluated because there are
" integrated rate tests". to " integrated application for amendment involves no no physical plant modifications or leak rate tests"in Specification 4.4.1.1.4; significant hazards considerations. changes involved.
correct misspelled words in Loco / Public Document Room (3) Involve a significant reduction in a Specifications 4.4.1.2.1.a and 4A.1.2.1.f; location:Tomlinson ubrary, Arkansas margin of safety because organizational change Specification 4.8 to correct the Tech University,Russellville Arkansas control and accountability are enhanced title to read " Emergency Feedwater 72801. by these changes.
Pump Testing"; correct a misspelled Atrorneyforlicensee Nicholas S. The NPC staff hs nviewd th word in the Bases of Specification 4.9; Reynolds, Bishop Uberman, Cook, licensee's determination and agrees add appropriately "4.21 Sprinkler Purcell and Reynolds,120017th Street, with their evaluation in this regard anh.
Systems" which apparenti was NW., Suite 700, Washington, DC 20038.
- themfom, proposes to determine that the removed in the licensee's uplication of NRCPm/ect Dimetoriohn F, Stolz.
proposed change does not involve a the page 110t; correct a misspelled word Carolina Power and Ught Co., Docket significant hazards consideration.
in the Bases of Specification 4.28;
. correct the title in the Index of No. 50-261. H. B. Robinson Steam Loco / Public Document Room
" Surveillance Standards" to read Electric Plant Unit No.2, Darlington Locotiont ifartsville Memorial Ubrary.
" Surveillance Requirements": and County, SC }{ome and Fifth Avenues. l{artsville.
correct a misspelled word in the Bases Date of amendment mqueste March 9, South Carolina 29535.
of Specification 2. 1987, Attorney for //censee: Shaw, Pittman.
- 5. Change Specification 6.5.2.2 to Description of orrendment mquest: Potts, and Trowbridge,2300 N Street, allow the Safety Review Committee The proposed amendment would revise NW., Washington. DC 20037.
(SRC) to be composed of at least eight Technical Specification (TS). Section 6.0, NRCPro/ect Dimetor: Lester S.
members in addition to the chairman. Administrative Controls, for the If.B. Rubenstein.
l
.2333d Feder:1 Regist:r / Vol. 52. No. 77 / Wedn:edry. April 22, 1987 / Nstices Commonwealth Edison Co Docket Nos. accident occure. A new or different kind This tubing had deyaded to the extent STN 56-454 and STN BM55. Byron of accident is not created as a result. that through wall holes had developed Sution. Unit Nos.1 and 2. Ogle County, 3. Involve a significant reduction in and leakage had occurred.The RCFSs II, the margin of safety.ne addluon of a dwign funcuan is to remove heat from new Technical Specification does not the containment stunosphere and Date of application foromendments: delete the requirements for o bility transfer it to the servios water system M:rch 5.1987. of any other Technical Spect tion. under both mermal and accident DescWption of amendments requese Requiring high energy line break eensore constions,ne pluging ofleaking coil ne amendments would revise the to be operehle prevents the potential for tubes was semp damage w eefety.reieied eyetems .nd werefore, a me.readeing this function.
Scaison w.e ,ianned T,,-pgh
,, Energyspengyg,',gt,y,,* i structores in the maxiliary building.nis to replace the omleting RCFC owvice senews be opneble. will not reduce the margin of eefety. water cooling seile with new coils of a Boeisforproposedno significant TM Conske%n W proddd horoids considemtim determination: guidace conowsdag to appliceHon d W M wedd && he The staff has evehiated these proposed hydeum " ----
enwndmente and de d that they me suda;de for hwrunning wheew a m gde e4 hu -
significa h
-d- - si.nif- - i., ,r.a.ntnge beenrds am ,i.e cons.ide.ra.t.
. m1 of ion existe to,appede,the.e intended ce,ebol e .e c c eet removal
,1.c.easin, fik[y irrvolve a signi e coifend ir reYe te sto signincant hasarde caseiderations if consideration. Eaample (ii) relates to a th2 proposed amendmente do not:(1) change that cor.etitutes an additional with thistion effort was of the R a be.ne1 to atmplify involve a significent incruee in the the probability or consequences of an hmitation. restriction, or control not olmpfification of the RCPC by the presently incidd la &e Tecluded ehh h hl**
- 6 accident previously evaluated; or (2) Sp,cifg.g.,; go, ,,,,pg ** * "*" would reedt in increesd reh ty,
' e ased for the two exieung modes ifheren i den y thw .'h M ebenge le of opere6on, norseal and eccidet, was c;ccident previously evaluated; or (3) to Enample (u) since te change le we si i cant reduction in a prow &g ddiuond hastadoms.
- part this h
"* " ' 8'
- the FRARed not take any credit for any Die amendment regeeses the addition gneg cf a new Technical Specification h*' T SpMSos6 es. e5ects of eentainment cleanup from the ne propM mehunt W exie esistus tore and HEPA requ! ring high hae brook has break ledenen sensore k isolation sensors operable. Mees *o % pere. Carrently the Technical '"I' 'U"'
sensore automatically detect and leolate AI""'
- 88'et e air Sow paths. and the Spec 68easons do not have high emergy line breaks in the gesam requiremmets for high emergy [ine break soeultant ased to Generator Blowdows and Aandliary **d** *** ' ,eoteste the accident Steam systems before eenhary beGding leda6on n es,gere, sensors'd bee on b above The ROC modiScedon had envtreuunestal constione exceed considerauona, du etaH W deurmind the followiss to:
predicted values. "" t of the RCPC heat that this change dose not levelve ae The
' cant i
d change does not involve significant hasarde consideration.
hasards consideration Loos /PublicDocument Aoom M
.-aemoeal of the notehme sepasstore beoeuse opwetion of Byron Unite 1 and locasion Rockford PubbcIJbrary.216N. aene,el of the HEPA Riters 2 in accordance with this change would Wyman Street. Racidord. Ilhoolo 81103. Air sentroldampere pumamently
- 1. Involve a signiocent increase in the placedin the essident mode leba a d Beale Fire probability or consequences of an National Plaan. 4and Floor, Chieses. Tesimleal coton 43.1.AJ eccident previously evaluated. Requiring Ilknote 40003 stateev'Esch esoler damper shallbe high energy line break isolation sensore NRCprojectDimssor: Steven A. stroked to the accident position and the to be operable does not affect the Varga. Poeloon inecouen etwcked during each probability of an accident occurring.De refueling outage." la addition, the basis consequences of an accident may h-= wealth Eneau Co, Desbet Nee. for tide section states:'%e testing cetually be decreased. The sensore are sMes and gMB4, Else Nuclear power proyez le edequate to ensure continued designed to detect an increase in Station Unit Nos. t end 2. Lake Ceesty, availebutty of each of the fan coolere. It temperature due to a high energy line IL wul further provide eseurence of the break and initiate e signal to close Date of application foramendments; continued operabill of those fan cooler valves to isolate the source of high December 4.1986. supplernented March componente esed y during an trergy. Die encores that opersuon of 3.1987, accident altueuon."
eq alpment le not impacted by an Description of amendments requeste - nue, the intent of the RCFC refueling cdverse environment.nerefore, when This proposed amendment clarifies surveillance le to ensure that the equipment le requ4ed to be operable to Sectione 33 and 44-Reactor accident air flow path is available. A '
respond to an accident condition, there Containment Fan Coolere followig a simple verification that the dampere le a greater probability it will be recent modification to the reactor remain in the accident posttion setlefles evallable. containment fan coolere (RCFC) and the surveillance requiremente.
- 2. Create the possibility of a new or converte the entire section into the Therefore, the placement of the control different kind of accident from any Standardised Technical Specification dampers in the accident position does previounty analyzed, ne additional format, not preclude the performance of the requirements in, posed by the new in 2004, the heat enchangers for Zion's surveillance requirements of Section 4J.
Technical Specificauone are designed to se RCPC's were enh6b6 ting depredation This proposed amendment also alters limit the po ential conneauences tf as of the service water cooling coil tubing. the formet of Sectione 3.5 and 4.5 to the
Federal Register / Vol. 52, N*:. 77 / Wednesday. April 22,1~7 / N:tices 13333 Standardised Technical Specification conseguances of any accident hasards consideration exists, format.
My evaluated. Commonwealth Edison Company has r.
Basisforproposediso significcat "* *
- hozords considemt/ar, determination 10 Criterion 2 application involves no signtScant CFR 50.92 states that a proposed %e clarification of the existing intent .hasards consideration.
amendment wul involve a no .<-inm+ of the Zion Technical Specincations and W staff has reviewed the licensee's hazards consideration if the proposed the sharation of the format of Section no signincent hasards consideration amendment does not: 3.5 and 4.5 has no effect on any of Zion's determination and agrees with the (1) Involve a significant increase in systems or structures. As discussed licensee's analysis. Accordingly, the the probability or consequences of an above. the RCFCs heat removal Commission proposed to determine that accident previously evaluated; or capability and reliability has been the proposed changes to the Technical (2) Create the possibility of a new or increased.%ese improvements do not Specification involve no significant different kind of accident fmm any result in any additional system hazards mnsideration.
accident previously evaluated; or interactions.Thus, there can be no . Loco /Public Document Room (3) Involve a significant reduction in a potential for any previously unanalyzed location: Waukegan Pub!Lc Ubrary.128 margin of safety. malfunction or component failum. N. County Street, Waukegan. Illinola in addition, the Commission has The RCFCs are intended to remove 00065.
provided guidance in the practical energy from hside of the containment Attorney to licensee P. Steptoe. Esq.,
application of these criteria by structure following a main steam line Isham. Uncoln and Beale. Counselors at publishing eight examples in 51 FR 7751. break or a loss of coolant accident.%e law, %ree First National Plaza. 51st The licensee provided the following analyses for these accidents contained Floor, Chicago. Dhnois 80002.
discussion regarding the above three in Zion's FSAR have been reviewed. 3.RCProjectDirector Steven A.
criteria: Based upon the lack of system interaction discussed above, the yarga Criserion 2 underlying physical modification. will Consolidated Edison (N==p==y of New
%e proposed change, and the not affect any of the pre-existing York Dodet No.so-a47,ladian Point underlying modifications. have no effect accident sequences. Nuclear Generating Unit No.2. .
on the operation of Zion's RCFCa.The Hus, this proposed amendment does Westabaster Ceemty, New York physical modificatica has not affected not create the possibility of a new or the availability of the ment air Sow different kind of accident from those
&te of anenWngse March it, path during accident conditions. Rather. previ2usly evaluated. 1967.
the physical mediacanon has resulud in Description of Amendmentsegoest:
the accident Dow path being Criasrion 3 The proposed amendment would revise continuously available and increased %e RCFCs will remain continuously the Technical Specifications to include heat removal capacity. %us. the RCFCs available to perform their intended station batteries nos. 23 and 24 under are always available to perform their safety function.%e physical the existing provisions for station safety function. modifications to the RCFCs have batteries nos. 21 and 22. Currently, the Chapter 14 of the Zion PSAR asemnes resulted in more efficient and reliable Technical Specifications numerically list that three RCFCs are cperating in the operation.%ua. the margin of safety only batteries nos. 21 and 22.ne post-IDCA containment envimnment to has been increased as a result of the pmposed change will add batteries nos.
remove energy from the containment physical RCFC modification. 23 and 24 wherever batteries nos. 21 and atmosphere. The ability of Zion's RCFCs Ifowever, the proposed amendment 22 are cited. The actual modification to to perform this function has been only involves the clarification and the Indian Point 2 battery system was increased as a result of this physical reformatting of the Zion Technical reviewed and accepted in NRC Safety modification.%e heat ressoval Specifications which does not affect the Evaluation dated May 2.1980.%e capability has been increased and the safety function of the RCFCs. Since the modification eliminated the automatic need to automatically transfer from the RCFCs ability to remove energy from transfer of loads between the original normal to the accident air flow path has inside of the Zion cxmtainment structure redundant safety-related batteries 21 been eliminated.Thus, the RCFCs will be ansitered by this administrative and 22 by using additional batteries 23 ability to perform their designed clarification. bre will be no change in and 24 as " swing buses." Each D.C.
function has not degraded. the margin of safety due to the proposed transfer circuit was provided transfer The modification of the verb " stroke" Technical Specification amendment. capability between batteries 21 and 22 to the verb " verify" merely clarifies the This proposed change involves and batteries 23 or 24. De modification intent of the existing surveillance to clarifying the existing intent and was made to improve the reliability of ensure that the accident Gow path is reformatting of Sections 3.5 and 4.5 of the de power system.
continuously available.The existing the existing Zion Technical Basis forproposedno significant Technical Specification surveillance Specifications. Thus, example (i) is bazords consideration determination:
requires that the dampers be stroked applicable in this instance. Example (i) 'Ihe Commission has provided guidance and verified in their accident positions reads as follows: concerning the application of the every refueling. Dere is no requirement (i) A purely administrative change to standards in 10 CFR 50.92 by providing
, to stroke the dampers back to the technical specifications: for example, a certain examples (March 6,1980 51 FR normal flow path position.%us the change tc echieve consistency 7751] of amendments that are not likely modification of b verb
- stroke" to the throughout the techmcal specificauen, to involve a significant hazards verb " verify" merely formalizes the correction of an error, or a change in consideration. ne propoced change is preexisting intent of the Zion Technical nomenclature. enveloped by example (ii) which relates
! Specificauona. Therefore, aina the application for to changes that constitute an additional Based upon the above discussion, the amendment satisfies the ef teria limitation, restriction or control not i proposed amendments do not involve a specified in to CFR 5032 and is almilar presently included in the Technical i
significant increase in the probability or to examples for which no significant Specificauona.The staff proposes to
r 13336 Federal Register / Vcl. 52, No. 77 / Wednrsd:y, April 22, 1987 / N:tices determine that the amendment does not concluded that these tests are necessary to Basisforproposed30 sionificont involve a signification hazards ensure reliable reactor trip breaker operation. hozords considemtioredetermination:
consideration since it adds restrictions The Commission has provided ne Commission's staff has determined not currently in theTechnical guidance concerning the application of that the proposed changes are Specifications. Its standards set forth in to CFR 50.92 administrative b that they correct errors Loco / Public Document Room for no significant hazards consideration and inconsistencies in the TSs.
locotion White Plains Public Library,100 by providing certain examples (51 FR With respect to the first item. the Martine Avenue, White Plains,New . 7744). One of the examples of an diverse containment isolation function York 10610. amendment likely to involve no or HP! Isolation" was added to the Attorneyforlicensee: Brent L significant hazards consideration relates plant and the Technical Specifications Brandenburg. Esq,4 Irving Place,New to changes that (ii) constitute additional as a part of the NUREG-0578 Short York. New York 10003.. limitations, restrictions, or controls not Term Corrective Actions. At that time, NRCPmfect Director: Steven A. presently included in the Technical the licensee mistakenly Licluded the Varga. Specifications.The proposed ** Manual Initiation" functional group in Duke Power Co Docket Nos. 50-30, amendmentof theTechnical the specification. A specific manual .
and 50-370, McGuire Nuclear Station. Specifications matches the example initiation circuit for the diverse Units 1 and 2. Mecklenburg County, NC because it would impose additional containment isolation does not exist, surveillance requiremente for the reactor therefore, this functional group should Date ofomendment request trip breaker undervoltage and shunt trip be deleted from the Technical -
December 7,1985, as supplemented attachments not presently included in Specifications.
March 10 and April 2.1987. the Technical Specifications. The second item is simply a typing Description of omendment request:In The above proposed changes would 51 FR 22234 dated June 18,1986, the error. The inequality sign in item 5.a.5.
require testing of the undervoltage and (Table 3.3-4)"RCS Pressure Low (Hpl Commission noted that amendments shunt trip attachments in accordance hid been proposed to change the Isolation)" must indicate a setpoint of with Generic Letter 85-09 for required greater than or equal to 1500 psig.
Technical Specifications (TSs) to add actions based on generic implications of some of the changes required by the The Commission has provided the Salem ATWS event.Therefore the guidance concerning the appheation of NRC in its Generic latter (GL) 85-09. staff proposes to determine that the standards in 10 CFR 50.92 by providi'ig
' Technical Specifications for Generic proposed amendments do not involve a Letter 83-28, item 4.3." Item 4.3 of GL certain examples (51 FR 7750). One of significant hazards consideration. the examples of actions involving no 83-28.
- Required Actions Based on This notite supplements the proposed Generic Implication of Salem ATWS significant hazards conAderations is changes addressed in 51 FR 22234 and example (i), a purely administrative Events," established the requirement for does not otherwise alter those previous change to the technical specifications:
automatic actuation of shunt trip proposed changes nor the Commission's cttachments on reactor trip brea,mers. For example, a change to achieve prior proposed determination of no consistency throughout the technical Additional requirements of GL 85-09 significant hazards consideration.
regarding items ta be addressed by TSs specifications, correction of an error, or Loco 1Public Document Room a change in nomenc! .ture.The licensee were noted to be outside the scope of 51 location: Atkins Library, University of has determined, ar2 the Commission's FR 22234.ne licensee's supplemental North Carolina. Charlotte (UNCC) requests of March to and April 2,1987 staff agrees, thet th= changes proposed Station. North Carolina 28223.
propose to add these additional Attorneyforlicensee:Mr. Albert Carr, in this suendiaent *..ylication are requirements of GL 85-09 to the TSs. Duke Power Company,422 South administrative inter ded to correct Specifically, the additional requests Church Street, Charlotte, North Carolina errors and thur accu *ately reft:t the would add the reactor trip bypass 28242. actual plant configuratin The.afore, breaker to TS Table 4.3-1. " Reactor Trip the Commission proposes to determine ARCN/ect Director: B.J. that the application for amendment System Instrumentation Surveillance Youngblood.
Requirements." The associated table involves no significarit hazards Florida Power Corp., et al., Docket No. considerations.
entries for operational test frequencies 50-302, Crystal River Unit No. 3 Nuclear LocalPt;blic Document Room for the shunt trip and undervoltage trip Generating Plant, Citrus County, FL locatior Crystal River Public Library, w c ei ! ce is quire w uld be Date ofomendment request: January 'W.First Avenue,CrystalRiver, cdded by table notation consistent with 241985. as supplemented February 17 a 32829 , ,
GL 85-09. The Bases ould be supplemented to ad es these Descf/ption ofamendment requestf Senior Vice President and General De amendment proposed by the Counsel. Florida Power Corporation. I s forp no significont licensee would make corrections to the P.O. Box 14042. St. Petersburg. Florida hozords consideration determinotion: Engineered Safety Features Actuation 33733. .
The proposed changes to the Techtdcal System (ESFAS) Instrumentation AWCPivfect Director-John F. Stolz.
Specifications are submitted by the Specifications.The proposed corrections Florida Power Corp., et al., Docket No.
licensee in response to GL 85-09. In CL am 50-302, Crystal River Unit No. 3 Nuclear
- 85-09 the Commission notes its conc sion at d2 5 h f n Generating. Plant Citrus County. FL Initiation (ifPi lsolation)" from " Reactor Date ofomendment request: February Technical Specification changes should be Building isoletion", 17,1987.
proposed by hcensees to exphcitly require independent testmg of the undervoltage and
- 2. Reverse the inequality sign for item Description of amendment request:
5.a.5. (Table 3.3-4) "RCS Pressure Low This submittal would update airlock p t an i epe de t s ofthe (IIPlisolation)" so that the setpoint surveillance Technical Specifications control toom manual switch contacts during must be greater than or equal to 1500 (TSs) to reflect the exemption issued sah refuehng outage The Commission also psig. December 9.1986, for Crystal River Unit
Federal Register / Vol. 52, No. 77 / Wednesday. April 22,19e7 / N tices 13337 )
3 regarding the requiresnents of 10 CFR Atserneyforlicenser R.W.Neiser, for more accurate quantification and Part so, Appendtx 1. El.D.2(b)(ii).& Senkre Vice President and General assessment of these radiolodine releases exemption allows an air lock seal test in Counsal. Florida Power Corporation, due to condenser offges system gaseous place of the air look pressure test while P.O. Box 14042, St. Petersburg. Florida effluents. Adding this samphng system the reactor is in a shutdown or refuelirs 33733. . does not defeat nor degrade any existing mode.b amendment would change TS NRCPmpsetDisciort)ohn F.Senix. features and functions of the condenser 4.6.L3 so that the full pressure (Pa) test GPU Nuclear Corp., et al., Docket No. air removal system or offgas condenser will continue to be performed at least radiation monitoring system.
once per six months; however, prior to m h Mile Island Nuclar Standard 2.ne proposed amendment Station, Unit No.1, Dauphin County, PA ascending to Mode 4 the test will only should not create the possibility of a be conducted if maintenance activities Dose of amendinent mguest: Febmary new or different kind of eccident from had been performed which could have 3,1987 any accident previously evaluated.
. affected airlock saahns capability. Description ofomandment request: A Condenser offgas sampling does not The amendment would also delete a Condenser Vent Stack Continuous affect radiolodine releases, condenser footnote to E 4.6.1.3.a reostang to CFR lodine Sampler has been lastalled at operation, nor condenser radiation Part 50, Appendix J. TMI-1 to collect samples of radaotodme monitoring. The Condenser Vent Stack Basisforpmposedno significant during normal plant operations.nia Continuous lodme Sampler provides hozords considemtion determination: modification will provide the capabihty improved sampling capability, to allow to contmuously sample the condenser y g g This revision cha@e the Standard conforms Specifications (NUREG-0452) to the latest Technical offgas for radioactive gaseous lodme effluents which are released to the d
g, "y,"Un o
ea sd po el pbt "s of Substituting an airlock seal test for en atmosphere through the vent stack gatio"$1
,,h e e' us air lock pressure test while the reactor is during no mal condenser air removal. sampling is performed by another in a shutdown or refueling mode will Consequently, GPUN has submitted have no significant impact upon plant Technical Specikation Change Request systent operation or safety. Tests as desalbed Standard 3. The proposed =mM ===t (TSCR) No.157 to include additional sampling and analysis @ nts in should not involve a cignificant in the TSs will continue to dannonstrate containment lategrity. Table 4.22-2 which are commensurate reduction in a margin of safety because Previous air lock leekage test results with this new capability for continuous it requires additicnal sampling and have been within limits as specified by iodine sampling. Previous plar; analysis in the TSs vice reduced Ms. Based on the history of the capaylities were limited to grab sampling. With capability for containment air locks and previous test sampimg on a monthly frequency. continuous cond r offgas sampling.
results, it is unlikely that significant However, quantification of trace lodine the ability to quantify any release of leakage would occur. by laboratory analysis will be better radiolodine to the environment frorn Based on the above. the hosasee finds represented by continuous sampling. 9sseous condenser effluents will be the amendment will not: This will also facilitate annual dose improved. ,
(1) Involve a significant increase in calculations for unrestricted aress to Accordingly, based upon the above the probability or consequences of an ensure compliance with the limits ofIl discussion, the Commission proposes to accident previously evaluated because CFR Part 20 and Appendix I to 10 CPI determine that the appbcation for previous test results were satisfactory Part 50. amendment does not involve significant and significant leakage is not expected. Basis forpmposedno significant hazards masideration.
Both air lock tests c=tsure containment hazards consideration determinotscw A LocalPublic Document Room integrity, proposed amendment to en opemting location: Government Publications (2) Create the possibility of a new or license does not involve si ficant Section. SWe 1Ibrary of Pennsylvania, different kind of accident from any hazards considerations if three Education Building. Commonwealth and accident previously evaluated because standards provided by the t%mmission . Walnut Streets. Harrisburg, the proposed change introduces no new in 10 CFR 50.92(c) are met. Pursuant to Pennsylvania 17120.
mode of plant operation nor does it the provisions of to CFR 50.91, the Attorneyforlicensee Ernest L Blake, require a hysical modification. licensee has provided an analysis of no Jr., of Shaw, Pittman. Potts and (3)Invo ve a significant reduction in significant hazards considerations using Trowbridge,2300 N Street, NW.,
the magin of safety. Any reduction in the Commission's standards. The Washington DC 20(D7.
the margin of safety will be insignificant Commission's staff has revitwed the since air lock seal tests and air lock full licensee's proposed amendment and A'RCProject Director:Jahn F. Stolz.
pressure leakage tests will provide analysis. Each of the to CFR 50.92(c) GPU Nuclear Corporation, et al., Doriet assurance that the air lock will not leak standards is discussed below as it No. 50-289 Three Ffile Island Nuclear
- excessively not affect containment applies to the operation of TMl-lin Station, Unit No.1, Dauphin County, PA
. Integrity, accordance witn this TSCR for the The Commission's staff has reviewed Condenser Vent Stack Continuous Date of amendnunt rsguest. February the licensee's no significant hazards Iodine Sampler: 5,1987. 'i consideration findings and based on its Standard 1.W proposed amendment Description of amendment sequest: I
. review, agrees with the licensee's should not involve a significant incesse & proposed amendment revises the .
conclusions. Accordingly,the staff in the probability or cxmeequences of an operabihty requirements of the main /
proposes to determine that the accident previously evaluated because steam safety valves (MSSVs). In
- requested amendment does not involve the relesse of radiciodines is unaffected. particular, the amendment would allow Continuous condenser offges samphng operation at up to 5% full power with i a sig .ificant hazards consideration.
Loco /Public Document Room has no effect the probabihty or only two MSSVs per steam generator locotion: Crys tal kiver Public IJbrary, consequences of radiolodine releases to operable under a restrictive set of 668 N.W. First Avenna, Crystal River, the environment.The proposed conditions. The restrictions placed on.
Florida 32s29. amendment will only provide a means this operation include the following:
i I
1 . - _ .
. , --. .-. - - - . . - - - _ . - _ _ _ - _ - _ _ -. _-- _ __-_ _l
13338 Federal Register / Vol. 52. No. 77 / Wednesday. April 22,1987 / N: tic:s ~
1 1.The plant must have been total minimum valve relief capacity per consequences of an accidental release subcritical for at least >ne hour since steam generator using the two smallest of chlorine are reduced because the power operation above 5% power. safety valves per steam generator is proposed change provides additional 2.The Reactor Protection System almost twice the total calculated reactor assurance that the Chlorine Detection (RPSI overpower trip setpoint is set to coolant system heat gene ation under System (CDS) is operable and therefore less than 5% full power. the conditions allowed by the capable of promptly detecting the For power operation above 5% full amendment. By requiring two MSSVs chlorine release and initiating isolation power, the operability requirements for per generator, the total required relief of the centrol building ventilation MSSVs are not being changed.The capacity is almost four times the eIstem*
purpose of the amendment is to provide potential heat load, nerefore, operation for efficient in-place testing of MSSVs under the conditions of the amendment 2. Operation of the facility in following valve maintenance during would not involve a significant accordance with the proposed Cold Shutdown or refueling. reduction in a margin of safety. amendment should not create the Basis forpmposedno significant Accordingly, based on the above possibility of a new or different kind of l hozords considemtion determination: discussions, the Commission proposes accident from any accident previously i ne Commission has provided to determine that the proposed evaluated.The design basis event standards for determining whether a amendment does not involve significant related to this change is an accidental significant hazards consideration exists hazards considerations. reIeas' f chl 'n p d as stated in 10 CFR 50.92. A proposed LocalPublic Document Room ,dmd h nE effec n amendment to an operating license for a location:Covernment Publications possibility of creating a new or different facility involves no significant hazards Section. State ubrary of Pennsylvania, kind of accident from any accident l considerations ifit meets three Education Building. Commonwealth and Walnut Streets. Harrisburg, previously evaluated.The proposed standards as described in to CFR 50.92. amendment provides additional De Commission's staff has reviewed Pennsylvania 17128.
the licensee's analysis concerning no A ttorney for licensee: Ernest L Blake, assurance that the CDS is maintained significant hazards considerations and Jr., Shaw. Pittman. Potts and within the limits determined by the finds their analysis satisfactory. Each Trowbridge. 2300 N Street. NW., existing safety analyses and is unrelated standard is discussed in tum. Wsshington DC 20037. to the possibility of creating 9s new or Standard 1.ne proposed amendment NRCPm/ect Director: John F. Stolz. different kind of accident.
GPU Nuclear Corp, et al, Docket No. 3. Operation of the' facility in in the pro ab I o ences f M,Dme We Island Nuclear accordance with the psoposed accident previously evaluated.The Station, Unit Na.1. Dauphin County, PA licensee reviewed the 30-1 Final amendment should not involve a Safety Analysis Report (MiAR) Chapter Date of amendment request: February significant reduction in a margin of 14 accidents that depend upon operation 24.1987. safety.he proposed criteria constitute of the Main Steam Safety Valves Description ofamendment request! A an additional control not presently (MSSVal during some phase of the Chlorine Detecion System was installed included in the Technical Specifications.
accide.t. Seventeen accidents were at TMI-1 as a result of control room Therefore, the overall margin of safety evaluated. The licensee's review habitability studies conducted as part of for the plant is increased.
Indicates that operation under the NUREG-0737.The Chlorine Detection The Commission has provided proposed amendment will not impact System provides an alarm and isolates guidelines pertaining to the application the events analyzed in Chapter 14 of the the control room in the event of an of the three standards by listing specific TMI-1 FSAR and the TMI-1 Reload onstie chlorinef as release. %e examples in 51 FR 7750. De proposed purpose Reports remain bounding.Therefore, the of this propose amendment is to amendment is considered to be in the proposed amendment to allow MSSV provide operability and surveillance requirements on this new system. same category as example (ii) of testing does not involve a significant amendments that are considered not increase in the probability of occurrence Bosisforpmposedno significant or consequences of an accident hozoit/s considemtion determination: In likely to involve significant hazards 10 CFR 50.92, the Commission provided consideration in that the proposed previously evaluated.
inree standards fcr when a proposed change constitutes an addition control Standard 2.The proposed amendment should not create the possibility of a amendment does not involve a not presently included in the Technical new or different kind of accident from significant hazards consideration.The Specifications, any accident previously evaluated. licensee's no significant hazards Accordingly, based on the above Results of various licensee analyses consideration, as presented in their discussions, the Commission proposes itdicate that MSSV operability February 24.1987 application. is to determine that the proposed requirements are conservatively acceptable to the NRC staff. A amendment does not involve significant bounded by the existing safety analysis discussion of each of the three hazards considerations.
In all cases.The proposed amendment standards follows:
{
j does not change the physical design, 1. Operation of the facility in installation, operation or maintenance of accordance with the proposed j, ["(
- ((]*
Section. State IJbrary of Pennsylvania. .
individual safety valves. Therefore, the amendment should not involve a proposed amendment does not create significant increase in the probability of Education Building. Commonwealth and Walnut Streets. llarnsburg.
the possibility of a new or different kind occurrence or consequences of an Pennsylvania 17128.
of accident from any accident previously accident previously evaluated.The f
evaluated, design basis event related to this change A ttorney for licensee: Ernest L Blake.
Standard 3.The proposed amendment is an accidental release of chlorine. The Jr of Shaw. Pittman. Potts and should not involve a significant proposed amendment has no effect on Trowbridge 2300 N Street. NW..
reduction in a margin of safety.The the probability of occurrence of this Washington, DC 20037.
licensee's analysis indicates that the design basis event.The potential NRCPm/ect Director: John F. Stolz.
l l
federal Regleter l'Vol. 82. No r7 / Wednesday. April 22, 1987 / N:tices 18339 CPU Nuclear Corp., et eL. Decket No. 10 CFR 80.92, the Commission provided Based on c.e above discussion, the as.ase.%ree Mile Island Nuclear three criteria for determining if a Commission proposes to determine tnat Station. Unit No.1. Daupbla County, PA proposed amendment involves no the proposed amendment does not Dateofamendmentsquest March 5. significant hasards considerations. Each involve a significant hazards standardis discussed as follows: consideration.
1987 Descri 1.no proposed amendment should Loco 1PublicDocumentRoom l
%1a Tecbtion of amendmentnquest:
cal Specification Change not involve a significant increase in the locat/on:Covernment Publications ;
probability or consequences of an Section. State IJbrary of Pennsylvania, Request (TSCR)(i.e., amendment accident previously evaluated.De . Education Building. Commonwealth and application) proposes to raise the re actor protection system (RPS) high accident analysis contained in the DG. Walnut Stmeta,liarrisburg.
1 Final Safety Analysis Report (FSAR) Pennsylvania 17126.
reactor coolant system (RCS) pressure trip setpoint from 2300 psig to 2355 psig. was conducted assuming a high RCS Attorneyfor heensee: Ernest L Blake.
Also, this TSCR proposes to raise the pressure trip setpoint of 2390 pelg.%Is Jr.,Shaw Pittman.Potts and arming threshold for the anticipatory conservatively bounds the proposed trip Trowbridge. 2300 N Street. NW.,
reactor trip on turbine trip from the setpoint of 2355 psig. %e anticipatory Washington, DC 20037 .
current 20% reactor power level to a reactor trip on turbire trip is an NRCPmfect Director: John F. Stolz.
level of 45% reactor power.This UCR additional safety feature which was not Mississippi Powse & IJght Co., System also proposes to modify the language of factored into FSAR analyses.He Energy Resources. Inc., South the basis of the Technical Specification purpose of this anticipatory reactor trip. Mississippi Electdc Power Assodation.
Safety Limit section concerning liigh as stated in NUREG-0737,is to reduce Docket No. 50-414. Grand Gulf Nuclear RCS Pressure Trip in order to accurately the frequency of challenges to the Station. Unit i. Claiborne County, MI reflect the history and meaning of the PORV. However, the PORV failing open current limit. is an event which has been analyzed Date of amendment mquest: March 19.
When TMI-1 was originally licensed, and found acceptable in the TMI-2 1967 the high pressure reactor trip setpoint FSAR.De consequences of this event De8Cf/Ption of amendment request: I was 2355 pelg. and the plant did not are not affected by changing the De amendment would make three i have an anticipatory reactor trip on anticipatory reactor trip setpoint. changes to the Techniaal Specifications !
turbine trip. As a result of the 30-2 nerefore the proposed amendment [UsM1) Revi,, se Figure 6.2.1-1. "Offsite accident, the Commission decided to does not involve a significant increase Organization to reflect changes in the reduce the challenges to and opening of in the probability or consequences of an management of licensing activities, the power operated relief valve (PORV). accident previously analyzed. emergency planritng plant engineering.
As documented in NUREG-0737 the an n t 2 constmchn and to reDect 2.The proposed amendment ahould the addition of the training and Babcock and Wilcox (B&W) designed n t create the possibility of a new or accounting groups which are now a part reactors were to satisfy the different kind of accideat from any of the Unit Organizatien;[2) revise Commission's concerns by (1) lowering accident previously evaluated.The Figure 6.2.2-1. " Unit 0:yanization." to the reactor high pressure trip setpoint to TMI-1 FSAR accident analyses bound teDect changes in management of the 2300 psig. (2) raising the PORV setpoint the changes proposed in this plant security group. records and office from 2250 psig to 2450 psig, and (3) installing an anticipatory reactor trip on amendment.Thus, the proposed services, plant technical support, and turbine trip when reactor power was amendment does not create the industrial safety, and to reflect deletion possibility of a new or different kind of of the position of Technical Assistant to greater than 20%. However, operational experience indicated that a number of accident from any accident previously the GGNS General Manager and unscheduled reactor trips were caused evaluated. transfer of the training and accounting as a result of these changes.In order to 3.De proposed amendment should groups to the Offsite Organization: and correct this undesired result, the B&W not involve a significant reduction in a (3) change U 6.5.2-2 to reflect a title Owners Group submitted two topical margin of safety.%e NRC Safety change of one of the members of the reports for NRC review. Specifically. Evaluations for the B&W Topical Safety Review Committee (SRC).
BAW-1890. " Justification for Raising Reports (BAW-1800 and BAW-1893) Basisforproposedno significant Setpoint for Reactor Trip on High conclude that changing these setpoints haranis consideration determination:
Pressure", was submitted in September still satisfies the requirements of - De Commission has provided 1985. and BAW-1893. " Basis for Raising NUREG-0737 regarding PORV openings standards for determining whether a Arming Threshold for Anticipatory and PORV caused small-break loss of significant hazards consideration exists Reactor Trip on Turbine Trip", was coolant accidents. Similarly, the - as stated in 10 CFR 50.92. A proposed submitted in October 1985.The NRC requirements on these matters embodied amendment to an operating license for a staff approved these topical reports by in IE Bulletin 79-05B are also met. Also, facility involves no significant hazards Safety Evaluations dated April 22.1966, returning the high pressure reactor trip considerations if operation of the facility 4 setpoint to 2355 psig and increasing the and April 25.1986.The basic conclusion in accordance with a proposed of the NPC Safety Evaluations was that arming threshold of the anticipatory amendment would not:(1) Involve a the high pressure reactor trip could be reactor trip on turbine trip will reduce significant increase in the probability or
. returned to its original value and the the frequency of automatic tdps and consequences of an accident previously arming threshold of the anticipatory thus reduce the number of challenges to evaluated: or (2) create the possibility of reactor trip on turbine trip could be plant safety systems. Analysis indicates a new or different kind of accident from increased to 45% with negligible changes that these setpoint changes result in a any accident previously evaluated; or (3) in the PORV opening frequency.The negligible increase in PORV epening involve a significant reduction in a proposed amendment is based on these frequency.Thus, the proposed margin of safety.
BAW Topical Reports. amendment does not result in a The licensee has provided an analysis Basis forproposedno significant significant reduction in a margin of of significant hazards considera' ions in hazards considerotion determination:In safety. its request for a license amendment.The I
13340 Fedesel Register / Vcl. S2, Ms. 77 / Wedneadry April 22, 1937 / Notices licensee has concluded with appropriate report to the Site Director,who wul emergency procedures.h changes to .
bases that the propesed amendment provide a higherlevel of management the Offsite Orgammation would satisfles the three standards in to CFR attention to these two functions.h strengthen the licensing project 50.92 and. therefore, involves no GGNS Unit 2 construction manager management and administrative significant hazards considerations, b would be downgraded from Manager to fhnctions, provide a more effective Superintendent to reflect the present management for Nuclear Plant '
NRC staff has made a pre!iadnary review of the licensee's submittal. A suspension of construction activities at Engineering support groups, place higher summary of staff's review fo!!ows. Unit 2. management attention on emergency He proposed orpenizational changes Change (2) consists of changes in the planning, decrease nan-== y would strengthen the GCNS Unit and Unit Organisation.The Technical emphasis en Unit 2 construction and Offsite Organizations.He changes Sapport Superintendent, who presently facilitate broeder and higher level would provide more efficient reports to me Manager, Plant management attention to training and administration of plant licensing and Operations, would report to the accoenting activities.He changes to the engineering functions. Chain of Manager, Plant Sup; et.%is transfer Unit Organization would more equally command functions would be changed would allow the Mar.c '. Plant distribute the woridoed between plant .
to ensure proper management attention Operations to concentrate his attention - support staff and plant operations staff, to designated areas of responsibility.. on daily operations and would more consolidate record and clerical s Consobdation of areas that have shnilar merely distribute the work load between functions, increase the management
- responsibilities would sueste a most the plant operations staff and the plant position level for security activities. and ,
2 afisctive cesanastional structure. support staff.This transfer would also delete an unnecessary techmcal Change (1) consists of 6enges he the balance the membership on the Plant assistant position.h PSRC Offsite Orpenization.W Nuclear Safety Review Committee (PSRC) so composition would be unchangad by Ucensing Department would be that there would be three members this reorganization but movement of the reorganized internally.%e representing plant operations functions Technical Support Superintendent from reorganization of the Nuclear usensing and three members mpresenting plant the operations staff to the support staff Department would provide a more support functions. He Industrial Safety would result in three members from effective licensing management function. Coordinator would report to the each functional group on the PSRC. The a mors centralized focus on Chemistry / Radiation Control proposed change to the SRC is only a communications with the NRC and a Suf, -;..;...i..;instead of the Manager change to the title of one of the members stronger administrative function.h Plant Operations to more closely and represents no change to the department would retain all the present osordinate industrial safety activities membership of the bod .
responsibilities except for amargency with radiation esfety activities.The For the reasons cited4above, the planning.& emergency pia group Offine Services Superintendent would proposed organisational changes would would report to the Assistant to Vice be downgraded to the position of a not: Involve a significant increase in ths President. Nuclear Operations which Supervisor reporting to the Records and probability or consequences of an would provide for higher level Material Superintendent.%is dange accident previously evaluated; or create management attention to amassancy would consolidate plant clerical the possibility of a new or different kind planning activities. N Nuclear Plant functions thus increasing management of accident from any accident previously Engineering Departammt would add two effectiveness of these administrative evaluated; or involve a significant middle level managers to assist the activities.& Plant Security Supervisor reductionin a margin of safety.
Director in managing six of the seven would be upgraded to Supertatendent Accordingly, the Commissica proposes engineering support groups in the without change in responsibilities or to determine that the proposed changes Department.His change would provide reporting level.%e position of - do not involve significant basards for greater management attention and Tedmiemt Assistant to the GGNS considerations, direction to the six enginsonns groups. GeneralManager would be deleted locolPublic Docement Room A seventh group. Operational Analysis, because necessary technical assis*2nce location: Hinds Junior College, would continue to report to the Director, is available from the sinnagare of the Metmadan ubrary.Raymond, thus continuing to provide independent . three -Arc ta reportmg to the Mississippi set 54 assessments of operational probleur.s to General 18 7 " nager. Plant Attorneyforlicensee:Nidolas S.
the Director,& responsibilities of the Operation: Manager. Plant Maintenance: Reynolds. Esquire. Bis . Uberman.
Nuclear Plant Er.gineering Department and Manager. Plant Support. Cook. Purcell and R 120017th would not be changed.h transfer of Change (3)is a change from the Street. NW., Washington. DC 20036.
the Training Superintendent and the present title. Director. Nuclear ucensing NRCProjectDirector WalterR.
Accountant (Controller) from the Unit and Safety, to Director. Nuclear Butler.
Organization to the Offaita Organization Ucensing.h word *1iefety" would be would be made to facilitate the proper deleted from the name of the department Noetheast Nuclear Energy Co Docket ,
to more clearly differentiate nuc; ear No.as-a45. Millstone Nuclear Power chain of cammand for the activities of on, Unit No.1.New landon County, these managers,h Traimag licensing activities (whid is primarily Superintendent is rampanaihla for the concerned with nuclear safety) from training of all employees including industrial safety activities. Date of amendmentisguset: February radworkers and plant modification h persons assigned to the newly 13.1987.
groups as well as Unit 1 operations staff. created positions would meet Description of amendmeniisgeest-
& Accountant's(Controller qualification requirements specified in & proposed amendment would lower responsibilities include cost control the Updated FinalSafety Analysis the Reactor Water Cleanup (RWCU) activities for plant modifications in Report.The proposed danses in system isolation set point from the addition to cost control activities for Technical Specifications do not involve existing reactor vessel low water level plant operations.The Training a change in plant hardware, plant to the low-low waterlevelDe Superintendent and Accountant will operating procedures, or plant proposed change would allow the
l Federal Register / W1. 52, N ,77 / Wednesday, April 22, 1987 / N:tices 13341 RWCU system to operate with a reactor Lowering the reactor vessel water The licensee has reviewed the i vessel water level that is four (4) feet level trip point for RWCU isolation proposed changes pursuant to to CFR lower than the level allowed by the could increase the amount of reactor 50.59 and has determined that they do existing Technical Specifications Table coolant water released into the reactor not constitute an unreviewed safety 3.7.1. building. (assuming a complete question.The probability of occurrence Basisforproposedno significant severence of the eight inch RWCU or the consequences of an accident or hazards considemtion determination system piping outside drywell malfunction of equipment important to The proposed change to the Technical containment) before RWCU system safety (i.e., safety.related) previously Specifications involves the automatic isolation by the low low water level evaluated in the final safety analysis action of the RWCU system isolation signal. However this increase is well report have not been increased. The valves which close on a low reactor within design basis accident values. For possibility for an accident or vessel wafer level signal. The low water primary coolant system breaks inside malfunction of a different type than any level signal loslates lines that penetrate the containment drywellincreased evaluated previously in the final safety the reactor vessel and the primary delay in closure of the RWCU isolation analysis report has not been created.
containment, and connect to primary valves caused by the change from low to There has not been a reduction in the systems which are not required during low. low set point signal will have little margin of safety as defined in the basis isolation conditions and are located effect,because the RWCU system is for any technical specification.
outside of the primary containment. itself a closed system. Changes in plant response for RWCU
, RWCU system isolation is achieved lowering the reactor vessel water system isolation time following a break by closure of redundant valves in the level set point, which causes RWCU in the RWCU system due to the RWCU 8 inch return pipe to the reactor system isolation, would eliminate proposed setpoint change are bounded vessel via the feedwater piping (closure unnccessary RWCU system isolations by current accident analyses. Therefore, of a check valve on backflow and that can occur following certain events, no new unanalyzed event is created.
closure of motor operated isolation e.g., main steam isolation valve (MSIV) The consequences of the proposed valve 1-CU-28) coincident with closure closure with subsequent indicated change will not impact the margins of of redundant motor operator isolation reactor water level decrease due to the safety in that the fuel cladding and the valves in the a inch pipe from the resulting pressure spike.ne licensee primary containment and primary reactor vessel via the recirculation loop stated in a March 13,1987 telephone coolant pressure boundaries will remain to the RWCU system (isolation valves conversation that operating experience intact. Although the proposed change 1-CU-2 and parallel valves 1-CU-3 and at Millstone Nuclear Power Station Unit could allow a greater quantity of core 1-CU-8). No.L(Millstone 1), has shown that cooling water to escape into the reactor RWCU system isolation on low level reactor safety could be enhanced by building following a RWCU system pipe limits the amount of reactor coolant that eliminating unnecessary RWCU system break outside the drywell, the can be released into the reactor building isolation following reactor scram. In the consequences are bounded by the in the unlikely event of a gross RWCU past, reactor scrams have caused the design basis loss of coolant accident system failure outside the containment indicated reactor vessel water level to -and the main steam line break.
drywell. Automatic closure of the decrease from the normallevel to the %e licensee has reviewed the RWCU systemisoletion valves low reactor vessel water level causing rd th following a postulated failure of the unnecessaryisolation of the RWCU b%ed cha50.92, and h a co clude$that primary coolant boundary that lowers system . During this postscram recovery they do not involve a significant hazards the reactor neel water level to the trip period the reactor feedwater control consideration in that these changes setting prev, 's increased radioactivity system throttles back to match the w uld not:
in the RWCU .ystem and provides drastically reduced steam flow. If or added assurance against uncontrolled 1. Inv Ive a significant increase in the when reactor vessel water level reaches releases of radioactivity from the RWCU the high level set point the feedwater pro ability or co se ces f an system. pumps trip off.The proposed changes to not affect Operating experience has shown that Table 3.7.1 of the technical they are bounded byacci a,nd do, dent reactor safety is compromised by too specifications make the RWCU system the current design basis many unnecessary (non accident) available during the postscram recovery analyses.
isolations of the RWCU system. period to bleed off excess water from 2. Create the possibility of a new or the reactor vessel preventing loss of different kind of accident from any Pressure transients and resultant coolant void collapse following main electric power to the main feedwater previously analyzed.This is a setpoint pumps because the feedwater could not change with no new associated failure steam isolation valve closure cause the indicated water level to decrease be reduced fast enough to avoid the high modes. Changes in plant response due to enough to activate the low water signal waterlevel pump trip signal.The the proposed setpomt change are and isolate the RWCU system.The proposed change reduces the risks bounded by current analyses.This capability to remove excess reactor associated with loss of feedwater. l.e., change does not affect the function or coolant through the RWCU system while failure of the feedwater pump (s) to operation of the RWCU system or the the feedwater control system throttles restart, and eliminates the time primary containment isolation system.
back to satisfy the new reduced consuming tasks of a dedicated control 3. Involve a significant reduction in a feedwater demand is thereby lost. room operator to restore the RWCU margin of safety,in that this setpoint Without this capability there is an system to the operating condition.%e change does not affect the protective increase in the risk that feedwater net benefit of the proposed change is the barriers and does not impact any safety pumps will trip (because of the slow increased ability to remove excess limits. ,
flow control response) due to high water from the reactor vessel via the The Commission has provided 1 reactor vessel water level. Failure to RWCU system during scram recovery guidance concerning the application of restart increases the frequency of periods thereby preventing high reactor standards in 10 CFR 50.92 by providing dependence on emergency safety vessel water level which causes reactor certain examples (51 FR 7750. March 6, 4 I
features to provide core cooling. feedwater pump trip. 1986).The changes proposed herein l
13342 Fed:c] Registir / Vol. 52, No. 77 / Wedn:sday. April 1987 / N: tic:s most closely resemble (but are not standards for determining whether a consideration is involved in the totally aligned with) example (vi). a significant hazards consideration exists proposed amendment.
change which may either result in some (10 CFR 50.92(c)). A proposed LocalPublic Document Room increase to the probability or amendment to an operating license for a . location: California Polytechnic State consequences of a previously analyzed facility involves no significant hazards University Ubrary, Documents and accident or may reduce in some way a considerations if operation of the facility Maps Department. San Luis Obispo, safety margin, but wh.fre the results of in accordance with the proposed California 93407 the change are clearly within all amendment would not:(1) Involve a Attorneysforlicensee Richard R.
acceptable criteria with respect to the significant increase in the probability or Locke. Esq., Pacific Gas and Electric system or component specified in the consequences of an accident previously Company, P.O. Box 7442, San Francisco.
Standard Review Plan. His is a setpoint evaluated:(2) create the possibility of a California 94120 and Bruce Norton Esg, change with no new associated failure new or different kind of accident from c/o Pacific Gas and Electric Company, rnodes. any accident previously evaluated; or (3) P.O. Box 7442. San Francisco, California Based on the information provided by involve a significant reduction in a 94120.
the licensee, the staff proposes to margin of safety. NRCPmfectDirector: Steven A.
determine that the licensee request The licensee has determined that the Varga.
involves no significant hazards proposed revision to the Technical consideration. Pacific Gas and Electric Co., Docket Specifications will not:
LocalPublic Document Room Nos. so-275 and 50-323, Diablo Canyon (1) Involve a significant increase in Nuclear Plant, Unit Nos.1 and 2, San location: Waterford Public Ubray,49 the probability or consequences of an Rope Ferry Road. Waterford. Luis OWspo Cmmty.CA accident previously evaluated because Connecticut 06385. (a) the radwaste storage area below the Date of amendment request: June 10.
Attorneyforhcensee Gerald Garfield, laundry was constructed as part of the 1986 (LAR 86-05).
Esquire, Day. Berry, a Howard. Original plant design as outlined in Description of amendment request:
Counselors at Law, City Place Hartford, FSAR Update Section 11.5.6 and (b)in The proposed --nhnts would Connecticut 06103-3M accordance with 10 CFR 50.59, a safety change the Diablo Canyon Nuclear NRCPmfect Directon Cecil O. evaluation was performed which Power Plant combined Technical n mas. determined that there were no Specifications for Units 1 and 2 to Pacific Gas and Electric Co., Docket unreviewed safety questions and that a clarify the requirements of Table 4.11-2 '
l l Nos. 50-275 and 50-323 Diablo Canyon Tedmical Specification change was not " Radioactive Gaseous Waste Sampling l
Nuclear Plant. Unit Nos.1 and 2, San required for construction of the laundry and Analysis Program" for containment l
Luis Obispo County, CA and the sesond radwaste storage purge releases by specitymg an l Date of amendment request: June 10, building.%e facility does not appropriate lower limit of detection eignificantly change the function of the (LID) for each type of analysis to b:
1966 (LAR 86 M). laundry / solid radwaste storage facility Description of amendmentrequest; performed.The present type of activity The proposed amendment would revise to TS Figure 5.1-3 in Technical analysis specified for principal gamma the Diablo Canyon Nuclear Power Plant Specification 5.1.3 is an administrative emitters with a 10-* LLD would be combined Technical Specifications for change that provides additional replaced with the following expanded Units 1 and 2 by adding the laundry / information and does not affect the entry in the table: (1) Principal gamma solid radwaste storage facility effluent accident analysis. emitters (noble gases) with a 10-* LLD, release points to Technical Specification (2) Create the possibility of a new or (2) 1-131 and 1-133 with a 10-*IlD, and (TS) Figure 5.1-3. " Map Defining different kind of accident from any (3) principal pmma emitters Unrestricted Areas and Site Boundary accident previously evaluated because (particulate) with a 10-811D. Also, the for Radioactive Caseous and Uquid the relocation of the laundry / solid type of activity analysis for principal Effluents."%e proposed change is in radwaste storage provisions and gamrna emitters for the waste gas decay accordance with an NRC staff request. proposed addition to the Technical tank.the plant vent, and the steam The laundry / solid radwaste storage Specifications do not significantly affect generator blowdown tank vent would be facility includes two buildings, one with the laundry / solid waste storage clarified by adding "(noble gases)." The a solid radwaste storage area on the functions as outlined in the ESAR or LLDs included in the revised Table 4.11-ground floor and a laundry on the changes in parameters governing normal 2 would permit detection at levels that second floor, and the other with only a operation. are no more than 3% of the dose rate solid radwaste storage area. As defined (3) Involve a significant reduction in limits of Technical Specification 3/
in the Standard Review Plan Sections the margin of safety because the 4.11.2.1.
11.1 and 11.5, Regulatory Guide 4.21, and proposed change to include the laundry / Basisforproposedno significant NUREG-0017 regarding gaseous source solid radwaste storage facility in the hazards consideration determination:
terms, the facility is not a major or Technical Specifications only involves %e Commission has provided potentially significant pathway for the inclusion of additionalinformation that standards for determining whether a release of radioactive material during is not presently included in the significant hazards consideration exists normal reactor operation, including Technical Specifications. (10 CFR 50.92(c)). A proposed anticipated operational occurrences. Accordingly, the licensee has amendment to an operating license for a Any airborne radioactive material determmed that the proposed change to facility involves a no significant hazards present in this facility will be principally the Technical Specifications involves no consideration if operation of the facility low-level activity in particulate form, significant hazards considerations.%e in accordance with the proposed which will be removed by HEPA filters NRC staff has reviewed the proposed amendment would not:(1) Involve a before release to the atmosphere. amendment and the licensee's significant increase in the probability or Basisforproposedno significant determination and finds it acceptable. consequences of an accident previously hazards considemtion determination: %erefore, the staff pmposes to evaluated;(2) create the possibility of a
%e Commission has provided determine that a no significant hazards new or different kind of accident from
Federal Register / Vol. 52, Nr. 77 / Wednesday. April 22, 1967 / N:tices 13343 any accident reviously evaluated; or (3) organizational changes and to change (3) Involve a significant reduction in a involve a cant reduction in a Technical Specification 6.5.2.9.a to margin of safety because the proposed margin of fety, specify that minutes of the General changes are administrative and do not The licensee has determined that the Office Nuclear Plant Review and Audit affect accident analyses, proposed changes will not: Committee (GONPRAC) meetings will Accordingly, the licensee has (1) Involve a signiScant increase in be forwarded to the President within 14 determined that the proposed changes to the probability or consequences of an working days following each meeting. the Technical Specifications involve no accident previously evaluated because ne changes to Technical significant hazards considerations.
the proposed changes only clarify the Specification Figure 6.2-1 and Technical ne NRC staff has reviewed the requirements of Table 4.11-2 and do not Specifications 6.5.2 and 6.7 reflect PC&E proposed amendments and the effect the accident analysis. corporate organizational changes. ne licensee's determination and finds it (2) Create the possibility of a new or title of the " Executive Vice President acceptable. Therefore, the staff proposes different kind of accident from any Facilities and Electric Resources to determine that a no significant accident previously evaluated because Development" was changed to hazards consideration is involved in the the proposed changes do not necessitate " President". proposed amendments.
physical alteration of the plant or The change to Technical Speci6 cation Loco /Public Document Room changes in parameters governirpormal Figure 6.2-2 reflects a plant location: California Polytechnic State plant operation. organizational chanoe.The plant University Library, Government (3) Involve a significant reduction in security organization is reporting to the Documents and Maps Department, San the margin of safety because the Assis'.ant Plant Manager. Support 1.uis Obispo, California 93407, proposed changes clarify the Services in order to provide additional Attorneysforlicensee: Richard R.
requirements of Table 4.11-2 and management oversight of the security locke, Esq Pacific Gas and Electric provide a more conservative organization activities. Company, P.O. Box 7442, San Francisco, containment purge 11D than that The change to Technical Specification California 94120 and Bruce Norton, Esq.,
presently required for principal gamma 6.5.2.9.a specifies that minutes of c/o Pacific Gas and Electric Company emitters (particulates) and for I-121 and GONPRAC meetings be forwarded to P.O. Box 7442 San Francisco, California 1-133. the President within 14 working days
- M 20.
Accordingly, the licensee has following each meeting to clarify the determined that the proposed changes to specified time period. Furthermore,it la NRCPmfectDirector: Steven A.
Varga. -
the Technical Specifications involve no impractical to prepare, review, significant hazards considerations. distnbute, and issue these minutes Padfic Gas and Electric Co., Docket ne NRC staff has reviewed the within a 14 calendar day schedule. Nos,50-275 and so.323. Diablo Canyon proposed amendments and the considering weekends, holidays, and Nuclear Plant. Unit Nos.1 and 2 San licensee's determination and finds it periodic unavailability of key personnel. Luis Obispo County, CA acceptable.Therefore,the staff proposes Basis forptryosedno significant Date of amendment request:
to determine that a no significant hazards considemtion determination:
The Commission has provided . December 19,1986 (LAR 86-12).
hazards consideration is involved in the Desenption ofamendmentrequest-proposed amendments. standards for determining whether a significant hazards consideration exists The proposed ccucn would an.end LocolPublicDocument Room Facility Operating Licenses DPR-80 and location: California Polytechnic State (10 CFR 50.92(c)). A proposed University Library, Government amendment to an operating license for a DPR-82 for the Diablo Canyon Nuclear Documents and Maps Department, San facility involves a no significant hazards Power Plant, Units 1 and 2, respectively, Luis Obispo, Cahfornia 93407. consideration if operation of the facility by deleting Unit 1 License Conditions Attorneysforlicensee:Richud R. in accordance with the proposed 2.C(6)h,2.C.(8), and 2.C(10), regarding i calculations for small-break LOCAs, Locke, Esq., Pacific Gas and Electric amendment would not:(1) Involve a Company, P.O. Box 7442 San Francisco, significant increase in the probability or control of heavy loads, and masonry California 94120 and Brnce Norton, Esq., consequences of an accident previously walls, respectively, and Unit 2 License c/o Pacific Gas and Electric Company, evaluated:(2) create the possibility of a Condition 2.C(7), regarding masonry l P.O. Box 7442, San Francisco, California new or different kind of accident from waffs. I any accident previously evaluated; or (3) The staff,in a letter of December 9. '
94120.
involve a significant reduction in a 1986 to the licensee, concluded that the NRCProjectDirector Steven A.
Varga. margin of safety. requirements of Section II.K.3.31 of ne licensee has determined that the NUREG-0737 regarding small. break Pacific Gas and Electric Co., Docket LOCA calculations have been met and.
proposed changes will not: <
Nos.50-275 and 50-323 Diablo Canyon (1) Involve a significant increase in the requirements of License Condition
- l Nuclear Plant, Unit Nos.1 and 2 San the probability or consequences of an 2.C(6)h in the Unit 1 full power license Lula Obispo County, CA accident previously evaluated because have been satisfied. ne staff concluded Date of amendment equest: August the proposed changes are all in a letter of October 24,1986 to the 14,1986 (LAR 86-09). administrative in nature, involving licensee, that the Unit 1 License Description of amendment mquest changes in nomenclature, organizational Condition 2.C.(10) regarding Phase B of The proposed amendments would revise structure, and time allowed to distribute the control of heavy loads is no longer the Diablo Canyon Nuclear Power Plant GONPRAC minutes. necessary, and no further action on this combined Technical Specifications for (2) Create the possibility of a new or item is required. ne staff concluded, in Units 1 and 2 to change Technical different kind of accident from any a letter of November 4.1986 to the Specification Figure 0.2-1, "Offsite accident previously evaluated because licensee, that the energy-balance Organization." Figure 6.2-2 " Plant the proposed changes do not necessitate technique as applied to the masonry Organization." and Technical a physical alteration of the plant or walls at the Diablo Canyon Plant is Specifications 6.5.2 and 6.7 to reflect changes in parameters governing normal acceptable, that the masonry walls are PG&E corporate and plant plant operation. appropriately qualified and that the l
l _- _
13344 Federtl Register / V:1. 52, No. 77 / Wednesday, April 22. 1987 / Notic s requirements set forth in Ucense NRCProject Dimctor: Steven A. (1) Involve a significant increase in Conditions 2.C.(10) and 2.C.(7) regarding Varga. the probability of consequences of an masonry walls in the Units 1 and 2 full accident previously evaluated because a P '
reload safety evaluation will be power licenses, respectively, have been satisfied. N 5 d yu performed for each cycle to confirm that
.. Nuclear Plant, Unit Nos.1 and 2. San Basisforpmposedno significant fuel assemblies with filler rods or ,
hozords considerotion determination: Luis Obi *P* Coun'I' CA vacancies in apecifled locations will meet the mechanical, nuclear, and
\
The Commission has provided Date of amendment request: February standards for determining whether a 10,1987 (LAR 87-01). thermal. hydraulic limits described in significant hazards consideration exists Description of amendment request: FSAR Update, Chapter 4 for fuel (10 CFR 50.92(c)). A proposed The proposed amendments would revise assemblies containing 264 fuel rods.
tmendment to an operating license for a the Diablo Canyon Nuclear Power Plant (2) Create the possibility of a new or facility involves a no significant hazards combined Technical Specifications for different kind of accident from any consideration if operation of the facility Units 1 and 2 to allow for the accident previously evaluated becau.=e in accordance with the proposed replacement of a limited number of fuel the cycle specific reload safety .
cmendment would not:(1) Involve a rods with filler rods or vacancies if such evaluation will confirm that a proposed significant increase in the probability or replacement is demonstrated to be core design with filler rods or vacancies consequences of an accident previously acceptable by a cycle-specific reload in specified locations meets existirg svaluated:(2) create the possibility of a analysis.ne current Technical design limits. -
new or different kind of accident from Specification 5.3.1 states that each fuel (3) Involve a significant reduction in -
eny accident previously evaluated; or (3) assembly in the core shall contain 264 the margin of safety because the involve a significant reduction in a fuel rods clad with Zircaloy-4.This proposed core designs with filler rods or margin of safety. amendment would allow for a reduction vacancies in specified locations will be The licensee has determined that the in the number of fuel rods per assembly within existing design limits.
proposed revision to the will not: and replacement of defective rods with Acordingly, the licensee has (1) Involve a significant increase in filler rods consisting of either Zircaloy-4 dete. mined that the proposed change to the probability or consequences of an or stainless steel, or with vacancies. The the Technical Specification 5.3.1. " Fuel accident previously evaluated because ability to replace defective rods wth Assemblies" involves a no significant the proposed changes are admmistrative filler rods or vacancies would permit ,
changes to the Facility Operating utilization of the remaining energy in IJcenses to delete license conditions no fuel assemlAies.
hazards W EC mfbu 4 consideration $W b longer needed on the basis of earlier Before replacement of any fuel rods, a [mp ,n e e d te safety and environmental evaluation ation and nds it staff evaluations. acceptable. nerefore. the staff proposes (2) Create the possibility of a new or would be made by the licensee on a different kind of accident from any cycle-specific basis as part of the reload to e aa accident previously evaluated because safety evaluation process.The core tt bb proposed amendments.
the proposed changes do not necessitate reload analysis ensures that the safety physical alterations of the plant or criteria and design limits, including Loco /Public Document Room changes in parameters governing normal peaking factors and core average hnear location: California Polytechnic State plant operation. heat rate effects, are not exceeded. An University Library, Documents and (3) Involve a significant reduction in explicit model with each discrete rod Maps Department. San Luis Obispo, the margin of safety becau.e the identified will be used to predict core Califomia 93407.
proposed changes are administrative performance based on actual core Attorneysforlicensee: Richard R.
and do not affect the accident analyses. inventory. The core reload methodology locke, Esq Pacific Gas and Eectric l
Accordingly, the licensee has does not change when filler rods or Company, P.O. Box 7442, San Francisco, determined that the proposed vacancies are used.The filler rods or California 94120 and Bruce Norton, Esq.,
amendments to the Facility Operating vacancies in a fuel assembly will be e/o Pacific Gas and Electric Company, License DPR-80 and DPR-81 involve no modeled as required for the specific core P.O. Box 7442. San Francisco, California significant hazards considerations. location. 94120.
The NRC staff has reviewed the Basisforproposedno significant NRCPmject Director: Steven A.
proposed amendments and the hazards considention determination: Varga.
licensee's determination and finds it The Commission has provided standard Pacific Gas and Electric Company, acceptable.Therefore, the staff proposes for determining whether a significant Docket Nos. 50-275 and 50-323, Diablo to determine that a no significant hazards consideration exists (10 CFR Canyon Nuclear Plant. Unit Nos.1 and 2, hazards consideration is involved in the 50.92(c). A proposed amendment to an San 1,uis Obispo County, CA proposed amendments. operating license for a facility involves a ,
LocalPublic Document Room no significant hazards consideration if Date ofcmendment request: March 13.
location: California Polytechnic State operation of the facility in accordance 1987 (LAR 87-02).
University Library, Government with the proposed amendment would Description of amendment request:
Documents and Maps Department, San not: (1) Involve a significant increase in The proposed amendments would revise .
Luis Obispo, California 93407. the probability or consequences of an the Diablo Canyon Nuclear Power Plant Attorneys forlicensee: Richard R. accident previously evaluated; (2) create combined Technical Specifications for Locke. Esq., Pacific Gas and Electric . the possibility of a new or different kind Unit 1 and 2 and to change the steam Company. P.O. Box 7442 San Francisco, of accident previously evaluated; or (3) generator water levellow setpoint from California 94120 and Bruce Norton, Esq., involve a significant reduction in a 25 to 15 percent of the narrow range c/o Pacific Gas and Electric Company, margin of safety. Instrument span.The specific change P.O. Box 7442, San Francisco, California The licensee has determined that the would be made in Table 2.2-1 " Reactor 94120. proposed change will not: Trip System Instrumentation Trip U -
Federal Register / Vol. 52, No. 77 / WIdnesdry. April 22, 1987 / N:tices 13345 Setpoints," of Technical Specification (1) Involve a significant increase in specify the number of hours the heaters 2.2.1 and the associated Bases. the probability of consequences of an must be operating on the control room Both units of the Diablo Canyon Plant accident previously evaluated because ventilation system to meet the intent of have experienced spurious reactor trips the steam generator waterlevellow the specification and addresses how the at low power from the steam generator coincident with steam /feedwater flow redundant equipment of each train of waterlevellow coincident with steam / mismatch reactor trip is not considered the ventilation system must be tested to feedwater flow mismatch signal. Plant for accident mitigation in accordance meet the surveillance requirements.
transients have caused the steam with the FSAR Update accident (2) Technical Specification 3.3.1, Table generator water level to drop below the analyses. 3.3-1. " Reactor Trip System low-level set point and a momentary (2) Create the possibility of a new or Instrumentation," would be revised to steam /faedwater flow mismatch signal different kind of accident from any modify Action Statement 2.c to clarify to be generated, resulting in reactor accident previously evaluated because the applicable thermal power level and trips. An actual flow mismatch condition the proposed change in setpoint does to delete "at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />" does not exist, but due to the sensitivity not eliminate the steam generator water from the Action Statement because the
. of the flow transmitters a signalis level coincident with steam /feedwater time interval for the quadrant power tilt generated. Changing the setpoint for the flow mismatch reactor trip. ratio (QIrrR) surveillance is already steam generator water levellow signal (3) Involve a significant reduction in specified in Technical Specification would significantly reduce the the margin of safety because the 4.2.4.2.
probability of reactor aips resulting proposed changes are administrative (3) Technical Specifica tion 4.3.1.1, from false flow mismatch signals. and do not affect the accident analyses. Table 4.3-1, " Reactor Trip System The effect of decreasing the steam Accordingly, the licensee has Instrumentation Surveillance generator water levellow setpomt on determined that the proposed Requirements," would be revised to the FSAR Update Chapter 15 accident amendments to the Facility Opera ing clarify that the plant heat balance analyses has been evaluated.The License DPR-80 and DPR-41 involve no surveillance requirement for the power analyses that could be affected are (1) sigmficant hazards considerations. range nuclear instruments is to be Section 15.2.8 " Loss of Normal The NRC staff has reviewed the Perfomd after15 pacent Bemal Feedwater," (2) Section 15.2.9. " loss of roposed amendments and the Power is exceeded, but before 30 Offsite Power to the Station Auxiliaries nsee's determination and finds it pucent 6cmal pownis reached, e (Station Blackout)," and (3) Section acceptable.Therefore, the staff proposes within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, whichever occurs first.
15.4.2.2. " Major Rupture of a Main to determme that a no significant ,
Basisforproposedno significant Feedwater Pipe." As stated in the FSAR hazards consideration is involved in the hazeds consideration determmation:
Update, accident mitigation for these propo' sed amendments. ne Commission has provided three accidents is provided by the steam LocoIPublicDocumentRoom o em t er a generator water level low. low reactor locatiotr California Polytechnic State [tand, gn f trip. The steam generator water level University Library. Government low coincident with steam /feedwater Documents knd Maps Department San U 5&92(c)). A proposeq amendment to an operating hcense for a flow mismatch reactor trip is not Luis Obispo California 93407. facility involves a no significant hazards considered for accident mitigation in the Attornej sforlicensee: Richard R. consideration if operation of the facility ansylses.The analyses demonstrate that locke, Esq., Pacific Gas and Electric in accordance with the proposed the steam generator water level low-low Company, P.O. Box 7442, San Francisco, reactor trip provides adequate California 94120 and Bruce Norton. Esq., amendment would not:(1) Involve a significant increase in the probability or protection for each of the accidents.ne c/o Pacific Gas and Electric Company, nsequences of an accident previously proposed steam generator weter level P.O. Box 7442, San Francisco, California evaluated:(2) create the possibility of a low setpoint of 15 percent narrow range 94120.
new or different kind of accident instrument span coincident with steam / NRCPm/ect Director: Steven A. previously evaluated; or (3) involve a feedwater flow mismatch reactor trip Varga.
would continue to provide backup Pacific Gas and Electric Co Docket e 8 I fe I w eact r Mp Nos. 50-275 and 50-323. Diablo Canyon %hlicensee has determmed that the Nuclear Plant, Unit Nos.1 and 2, San proposed changes will not:
Basisforproposedno s'ignificant Luis Obispo County, CA (1) Involve a significant increase in hozords consideration determination:
The Commission has provided Date of amendment request: March 13, the probability of consequences of an standards for determining whether a 1987 (LAR 87-03).
accident previously evaluated because a significant hazards consideration exists Description of amendment requese reload safety evaluation will be (10 CFR 50.92(c)). A proposed The proposed amendments would performed for each cycle to confirm that amendment to an operating license for a change the Diablo Canyon Nuclear fuel assemblies with filler rods or facility involves a no significant hazards Power Plant combined Technical vacancies in specified locations will consideration if operation of the facility Specifications for Units I and 2 to clarify meet the mechanical, nuclear, and in accordance with the proposed the requirements of three Technical thermal. hydraulic limits described in Specifications. FSAR Update. Chapter 4 for fuel amendment would not:(1) Involve a assemblies containing 264 fuel rods.
significant increase in the probability or ne specific changes would include consequences of an accident previously the following: (2) Create the possibility of a new or evaluated:(2) create the possibility of a (1) Technical Specification 4.7.5.1. different kind of accident from any new or different kind of accident from " Control Room Ventilation System," accident previously evaluated because any accident previously evaluated; or (3) would be revised to clarify the the cycle specific reload safety involve a significant reduction in a requirements for operating redundant evaluation will confin that a proposed margin of safety, equipment in each train of the control core design with filler rods or vacancies The licensee has determined that the room ventilation system during in specified locations meets existing proposed change will not: surveillance testing.He revision would design limits.
i
13346 Fedirst Register / Vol. 52, No. 77 / Wedn:sd:y, April 22,1987 / N tic:s (3) Involve a significant reduction in involve a significant reduction in a LocoIPublicDocument Room the margin of safety because the margin of safety. location: White Plains Public Library.
proposed core designs with filler rods or The following analysis was provided 100 Martine Avenue, White Plains. New l
l vacancies in specified locations will be by the licensee: York 10801.
l within existing design limits. 1.Does the proposed license Attorneyforlicensee: Mr. Charles M.
l Accordingly, the licensee has amendment involve a significant Pratt.10 Columbus Circle. New York.
determined that the proposed change to increase in the probability or New York 10019.
the Technical Specification 5.3.1 Fuel consequences of an accident previously NRCPmjectDirector: Steven A.
Assemblies" involves a no significant evaluated? Varga.
hazards consideration. ne proposed change does not he NRC staff has reviewed the Power Authority of ne State of New increase the probability of an accident York. Docket No. 50-286, Indian Point proposed amendments and the previously evaluated.The Authority has Unit No.3, Westchester County, NY licensee's determination and finds it analyzed the effect raising the acceptable. Therefore, the staff proposes containment ambient temperature to 130 Date of amendment request: March 4.
to determine that a no significant *F has on peak containment accident 1987.
hazards consideration is involved in the pressure during a loss of coolant Description of amendment request:
proposed amendments. accident.The results show that the ne licensee provided the following Loca1Public Document Room calculated peak containment accident description:
location: California Polytechnic State pressure is less than the containment University Llorary. Documents and (a) This revision seeks to amend the .
design pressure. Therefore, the Indian Point 3 Technical Specifications Maps Department, San Luis Obispo, consequences of an accident previously in response to Generic Letter 8M9 (GL California 93407. evaluated are unchanged.
Attorneysforlicensee: Richard R. 85-09) b -Y
.2. Does tye proposeg g; cense (1) Revising page 3.5-8 and Table 3.5-Locke, Esq., Pacific Gas and Electric amendment cmste the possibility of a , 2 to add limiting conditions for Company. P.O. Box 7442. San Francisco, new r diffennt kind of accident imm operation to the reactor trip breakers California 94120 and Bruce Norton, Esq any accident previously evaluated?
c/o Pacific Gas and Electric Company, and automatic trip logic; The proposed change of increasing the (2) Adding the reactor trip and bypass P.O. Box 7442. San Francisco, California 94120, containment ambient temperature 10130 breakers to the surveillance test F does not create the possibility of a requirements of Table 4.1,1; and NRCProjectDirector-Steven A.
new or different kind of accident than (3) Revising Item 20 of Table 4.1-1 to Varga.
Power Authority of The State of New reflect the standardized technical ni nt bien t p ature specification requirements for the York Docket No. 50-286. Indian Point ensures that the peak containment reactor protection automatic trip logic, Unit No.3, Westchester County, NY cecident pressure will not exceed the incl the o ered test basis.
Date ofcmeridment request: design pressure during steam line break
- pose or September 18.1985 and March 6.1987. or loss of coolant accidents.The Authority has evaluated these accidents
.g.g ,g g"{'.g.gM ,
Description of amendment sequest:
This amendment request was previously previously with a containment ambient Specificati,ons to facilitate the temperature of 120 'F. Herefore, this incorporation of GL 85-09 change 6 and l noticed on March 12.1986 (51 FR 8600).
The March 8.1987 amendment request analysis is not creating the possibility of improve the table a coherency by:
supercedes the previous request.The a new or different kind of accident. III M.aking minor spelling and format 3.Does the proposed amendment corrections to Items 1,14.16,21,28,30, purpose of these changes is to 31,32,34,35,36,38 and 39; implement Technical Specifications involve a significant reduction in a related to containment ambient margin of safety? . (2) Moving all footnotcs to the last temperature. Limiting containment The proposed change ofincreasing the page of the table; ambient temperature will ensure that the containment ambient temperature to 130 (3) Relocating Items 29 through 41 on peak containment accident pressure *F does not involve a significant sheets 3 through 5 to provide for a more does not exceed the design pressure of reduction in a margin of safety.%e even distribution; and 47 psig durino steam line break or loss Authority performed an analysis which (4) Deleting the footnote tying Item 35 of coolant accidents.This temperature calculated the peak containment to degraded grid modifications as the limit is not currently in the Technical accident pressure using a containment associated modifications are now Specifications, ambient temperature of 130 'F.The complete and Item 35 is now in e2ect.
Basisforproposedno significant results of the analysis for the LOCA Basisforproposedno significant hazards considemtion determination: show that the peak containment hazards considemtion determination:
The Commission has provided accident p essure increased to 41.2 psig. The Commission has provided standards for determining whether a which is an increase of 0.6 psig over the standards for determining whether a significant hazards consideration exists value for a containment ambient significant hazards consideration exists as stated in 10 CFR 50.92. A proposed temperature of120 'F. Applying this 0.6 as stated in 10 CFR 50.92. A proposed amendment to an operating license for a psig increase to the steam line break amendment to an operating license for a facility involves no significant hazards analysis results in a peak containment facility involves no significant h.zards
- considerations if operation of the facility accident pressure of 41.6 pelg. Both considerations if operation of the facility in accordance with a proposed resulting peak containment accident in accordance with a proposed amendment would not:(1) Involve a pressures are well below the amendment would not:(1) Involve a significant increase in the probability or containment design pressure of 47 psig. significant increase in the probability or consequences of an accident previously Based on the above, the staff consequences of an accident previously evaluated; or (2) create the possibility of proposed to determine that the proposed evaluated; or (2) create the possibility of a new or different kind of accident from changes do not involve a significant a new or different kind of accident from any accident previously evaluated; or (3) hazards consideration. any accident previously evaluated; or (3)
1 J
l Federal Register / Val. 52. Ns. 77 / Wedneed:y. April 22, 1987 / N;tices 13347 involve a significant reduction in a Attorneyforlicensee Mr. Charles M. ne following analysis was provided margin of safety. Pratt.10 Columbus Circle. New York, by the licensee:
%e following analysis was provided New York 10019. 2. Does the proposed license ,
by the licensee: NRCProjectDirector Steven A. amendment involve a significant l (1) Does the proposed license Varga. increase in the probability or . .. 1 amendment involve a significant Power Authority of %e State et New consequences of an accident previously . j increase in the probability or York Docket No. Bo-ass, Indian Point evaluated? i consequences of an accident previously Unit No.3, Westchester County.NY Neither the probability nor the l evaluatsd? consequences of an accident previously ;
Date of amendmentivguest March 8, Neither the probability nor the ggg7 evaluated in the FSAR are increased I consequences of an acc! dent are since the RVLis is a new post-TMI l Description of amendmentiequest modification aimed at enhancing the increased since new surveillance The licensee provided the following j requirements are being added to insure ~ description-Pl ant's overall safety. This goal is J increased reliability of the reactor The proposed changes to the Indian accomplished by providing the operators protection system.These new Point 3 Technical Specifications relate with an additional advanced warning of l requirements reflect procedures placed to the Reactor Vessel Level Indication a potentialInadequate Core Cooling in effect afterinstallation of the shunt System (RVLIS).The guidelines and (ICC) condition following en accident.
. trip attschment to the reactor trip recommendations of Generic Intter No. The proposed changes add operational i breakers These current procedures 83-37 have been utilized in preparing criteria for RVLIS in the Technical l independently test the undervoltage and revisions to Tables 3M and 4.1-1. Specifications. RVUS does not affect the '
shunt trip attachments during power Editorial change have also been analysis of any previously evaluated operation and independently test the included in the revised table (i.e., accidents and decreases the control room manual trip circuits during columns 1,2 and 3 headings added to consequences of small break loss of each refueling outage.Thus the Table 3M, Sheet 2 of 3: footnote coolant accidents.
proposed amendment provides marked *"" was moved to top of Sheet 2.Does the proposed license additional assurance that the reactor 3 of 3 Table 3.5-5). amendment create the possibility of a The p se of these p posed new or different kind of accident from e i viously v lu ed design ** "" **
basis accidents. In addition, editorial ch'[riat app limiting itions for
""I '
The possibility of a new or different changes are also made.None of these opebtion and kind f accident'is not created as changes increases the probability or the req ments forthe surveillance RVUS.The installation evidenced by the NRC Safety Evaluation consequences of an accident previously of RVUS willbe implemented in Report transmitted to the Authority on evaluated. accordance with the requirements of (2) Does the proposed licensa May 29,1964 which found acceptable NUREG 0737, item II.F.2, amendment create the possibility of a the proposed use of the Westinghouse
" Instrumentation for Detection of RVUS. This is based on the fact that the new or different kind of accident from inadequate Core Cooling." RVUS method and manner of plant operation is any accident previously evaluated? ne outputs are displayed on the plant possibility of a new or different kind if unchanged. The installation of RVUS is Qualified Safety Parameter Display accident is not created. The proposed not an !ni*.iating event of any accident.
Systsm.The system performs an input surnallance requirements autocalibration sequence by The system is bemg implemented in accompanying the recent shunt trip auto.natically injecting test signals Fponse 19 NUREG-0737. Item II.F.2, modification reduce the probability of directly into every input on a regular and NRC Generic Letter 83-37.
an Anticipated Transient Without schedule while the system is on line. 3.Does the proposed amendment Scram- The proposed limiting conditions of involve a significant reduction in a (3) Does the proposed amendment operation (LCO) and surveillance margin of safety.
involve a significant reduction in margin requirements are consistent with other %e proposed change incorporates of safety? Post Accident Monitoring Systems LCOs RVUS into the IP-3 Technical The proposed amendment provides contained in Table 3.5-6 (e.g. Reactor Specifications. RVUS will provide the
. additional assurance that the margin of Coolant System Subcooling ?largin operators with an additional way of safety for previously analyzed events Monitor, Core Exit %ermocouples, etc.)- detecting a potentialICC condition.
will not be reduced. By requiring the Basisforpmposedno significant Therefore, the operators' handling of an independent testing of the shunt trip and hozords considemtion determination: ICC condition will be enchanced and undervoltsge coils. the proposed The Commission has provided there will be no significant reduction in changes to the Technical Specifications standards for determining whether a a margin of safety.
increase the reliability of the reactor trip significant hazards consideration exists Based on the above, the staff preposes breakm. Thus, the proper operation of as stated in to CFR 50.92. A proposed to determine that the proposed changes the reactor protection system as amendment to an operating license for a -do n t invoIve a significant hazards assumed in the Safety Analysis for facility involves no significant hazards consideration.
Indian Point 3 is enhanced.%is assures considerations if operation of the facility
~
in accordance with a proposed Loco /PublicDocumentRoom that the margin of a.fety is not reduced. location: White Plains Public Library, l Based on the above, the staff proposes amendment would not:(1) Involve a 100 Martine Avenue, White Plains, New to determine that the proposed changes significant increase in the probability or consequences of an accident previously York 10601.
do not invol e a significant hazards consideration. evaluated; or (2) create the possibility of Attorneyforlicensee Mr. Charles M.
a new or different kind of accident from Pratt.10 Columbus Circle New York, locolPublicDocument Room location: White plains Public Ubrary, any accident previously evaluated; or (3) New York 10019.
100 Martine Avenue, White Plains. New involve a significant reduction in a NRCProject Director: Steven A.
York 10001. margin of safety. Varga.
I
1348 Federal Register / Vol. 52. No. 77 / Wzdn:sdzy, April 22, 1987 / N:tices ublic Service Company of Colorado. Colorado. P.O. Box 640. Denver, consequences of an accident previously iocket No. 50-267. Fort St.Vrain Colorado 80201-0840. evaluated; or (2) create the possibility of luclear Generating Station. Platteville, NRCPm/ect Director Herbert N. a new or different kind of accident from O Berkow. an accident previously evaluated; or (3) involve a significant reduction in a Date of omendment request: Public Service Electric and Gas margin d safety.
Jecember 23.1986. f'ampany. Dodat No. 56,354. Hope The proposed change does not involve Description of omendment request Casek Generating Station. Salem a significant increase in the probability the amendment would delete a table County, N] or consequences of an accident listing the shock suppressors on Class I arch piping systems (Table 4.3.10-1. Class I
@nen awn es previously evaluated became it 13 and 26.1987. constitutes a more limiting Technical _
Shock Suppressors) and the references Ho n9 sa e b the T cal nu ers o be in e t onal y re ove * *
- 8 ***"
from service for a period not to exceed be n the ref I rea i ors and p 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> without requiring an the Rec.2or Building Ventilation System ~pmposeMangh not create engineenng evalustion. In additimi. (RBVS) exhaust system isolation the possibility of a new or different kind certain typographical errors existing in dampers is greater than the combined f accident from an accident previously the Technical Specifications will be time for damper closure and the monitor evaluated because no hardware changes .
corrected. response.** The MAR identifies the to existing plant equipment are being Bosis forproposedno significont exhaust air transit time as being 12 proposed, and the dampers (and their hazards considemtion determinotion: seconds and the combined monitor associated isolauon umes) am Certain of the proposed changes to LCO response and damper closure time as mitigative in nature, not causal.
4.3.10 and SR 5.3.8 pertain to deleting the less than 11 seconds.The combined The proposed change does not involve snubber tables from the Technical monitor response and damper closure a significant reduction in a margin of Specifications and correcting time is the sum of the Refueling Floor safety because the change actuah typographical errors. These changes are Exhaust Radiation-High trip function increases the margin of safety by admir.'strative in nature and will have response time and the Secondary l no effect on the ability of the shock requiring a shorter damperliolation i Containment Ventilation System time, thereby bnnging the Technical l suppressors to protect the structural Automatic Isolation Damper Maximum Specifications into agreement with the l integrity of a safety related systems. Isolation time. Technical Specification FSAR analysis. ,
LCO 4.3.10.b has been chanoed. to . Table 3.3$3 gives the Refueling Floor Based on the above discussion, the clarify the difference in requirements for Exhaust Radiation-High trip function intentionally removing a snubber from staff agrees with the licensee's findings responce time as a maximum of 4.0 service end discovering an inoperable of no signincant hazards consideration seconds. Technical Specification Table associated with the proposed snubber.In the first case 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 3.6.5.2-1 gives the Secondary amendment. Furthermore, the staff notes allows time for repair or r9 placement of Containment Ventilation System snubbers during power operation. No Automatic Isolation Damper maximum that the proposed change is similar to an isolation time as 10 seconds. Combining Example (ii) amendment identified in engineering evaluation is required since the time period the snubber (s) are out of these values yields a combined monitor the " Final Procedures and Standanis or response and damper closure time of14 No Significant Hazards Considerations" service is known.
If a snubber is found inoperable and seconds, which is in conflict with the published in the March 6,1988 Federal Register (51 FR 7744) as not likely to the time that it has been in this FSAR statement above.
condition is in question, an engineering in its March 13.1987 letter, the involve significant hazards licensee requestad that the damper considerations. Accordingly, the staff evaluation is reouired to determine if any plant es ciutions or transients since isolation time of 10 seconds identified in proposes to determine that the Technical Specification Table 3.6.5.2-1 requested amendment does not involve i operability was last verified have l affected the associated piping and be revised to 7 seconds, as indicated in a significant hazards consideration.
its March 28,1987 letter. Such a change Loco 1Public Document Room equipment locotion: Pennsville Public Library.190 l
Based on the above evaluation,it is would result in a combined monitor response and damper closure time of South Broadway. Pennsville. New Jersey l
the staff's initial determination that operation of Fort St.Vrain in less than 11 seconds, thereby bringing 08070.
accordance with the proposed changes the Technical Specification into Attomeyforlicensee: Troy B. Conner.
will not:(1) Involve a significant agreement with the FSAR.The licensee Jr Esquire. Conner and Wetterbahn, increase in the probability or stated that the actual measured 1717 Pennsylvania Avenue. NW., .*
consequences of an accident previously response times are already within the Washington. DC 20006.
evaluated:(2) create the possibility of a proposed response time limits. NRCPm/ectDirector: Elinor G. ~
new or different kind of accident from Bosisforpmposedno sigmficoat Adensam.
any accident previously evaluated or (3) horoids consideration determinotion: Sacramento Municipal Utility District, involve a significant reduction in any The Commission has provided margin of safety. Accordingly.the staff standards for determining whether no proposes to determine that the proposed signif cant hazards consideration exists
'[Gb gS am as stated in to CFR 50.92(c). A proposed hII' CA changes will not involve a significant amendment to an operating license for a Dateofamendmentrequest October hazards cansideration. 2.1986,as supplemented April 1.1987.
Loco /Public Document Room facility involves no significant hazards location:Greeley Public Library City consideration if operation of the facility Description ofamendment request:
Complex 51uilding Greeley. Colorado. in accardance with the proposed The proposed Technical Specification amendment would not:(1) Involve a amendment incorporates Attorneyforlicensee Bryant O'Donnell. Public Service Company of significant increase in the probability or recommendations contained in Generic
i I
l l
Federal Cesister / V:1. 52, N:,77 / Wednesd:y, April 22, 1987 / Notices 13349 Letter 84-15." Proposed Staff Action to surveillance of critical plant systems. and 3 to establish the methodology to be improve and Maintain Diesel Generator The changes to the operability and used to determine the schedule for Reliability" and includes additions and surveillance requirements do not create implementation of NRC. required plant changes to the specifications which the possibility of a new or different kind capital modifications to San Onofre were necessitated by the addition of two of accident. Nuclear Generating Station, Unita 2 and Transamerica Delaval Diesel Generators The accident analysis in Chapter 14 of 3. Specifically, the changes would to supplement onsite emergency power the USAR is not changed by the addition amend the San Onofre 2 and 3 operating requirements. of the new diesels because the licenses to require the licensees to Basis forpmposedno significant additional capacity ensures that the implement and maintain in effect an hazards consideration determination power distribution system will support " Integrated Living Schedule Program The Commission has provided required safety related loads. The Plan"(%e Plan). De plan will be used standards for determining whether a system's interaction review shows that to schedule plaat capital modifications significant hazards consideration exists no new or different failure modes were that are either (1) required by the NRC (10 CFR 50.92(c)). A proposed created.This modification does not rules, orders or license conditions, or (2)
, emendment to an operating license for a therefore create the possibility of a new required to fulfill commitments made by facility involves no significant hazards or different kind of accident. the licensees to the NRC or other
-consideration if operation of the facility (3) Involve a significant reduction in a regulatory agencies.ne proposed in accordance with the proposed margin of safety. The changes instigated changes are consistent with the amendment would not:(1) Involve a by GL 84-15 improve operability and recommendations of Generic Letter 83-significant increase in the probability or surveillance requirements and therefore 20. " Integrated Living Schedule for consequences of an accident previously preserve the margin of safety.ney will implementation of Plant Modifications,"
svaluated: (2) create the possibility of a not reduce the margin of safety. which was issued by the NRC staff on new or different kind of accident from ne design basis for the emerger.cy May 9,1983.
any accident previously evaluated; or (3) power system is that a single failure of The Plan has as its goal the involve a significant reduction in a the system (including dier el generators) implementation of plant capital margin of safety. will not preclude the reactor protection modifications in a stable, controlled The licensee has determined, and the system and safety features system from manner with the implementation of Commission's staff agrees, that the performing their safety function. ne projects with the greatest potential for proposed amendment will not: modification of the emergency power enhancing the safe operation of the unit (1) Involve a sigmficant increase in system does not change this basis. generally given highest priority. Projects the probability or consequerices of an Based on the system's interaction cccident previously evaluated. of regulatory origin will be ranked using review and the design basis documents, the Westinghouse Analytical Ranking implementation of Generic Letter (GL) th's change will not reduce the margin of Process to specifically determine the 84-15 recommendations involves safety.The modification to the relative potential safety contribution of changes to the operability and emergency power system wdl provide surveillance requirements cf diesel each plant capital modification. The redundant emergency power sources for safety ranking will then be used as a generators.The changes add the control room, technical support requirements for new systems, improve center, and nuclear services electrical primary criterion in scheduling the requirements for existing systems, and building essential heating, ventilating. Pro et incorporate NRC recommendations. De and air conditioning systems. It will also changes demonstrate the operability of provide additional capacity for future 7,fj,$7ff[na e aYan m p wer required systems to ensure safe loads while ensuring that the existing cperation of the plant. Therefore, these resources, while at the same time emergency power system is not changes do not increase the probability overloaded. This, therefore, increases ,ffe'ai er consequences of an accident. the existing ma ,n of safety. f pro ct e ed necessary The proposed modifications to Accordingly, e Commission f r enhanced plant safety.The Plan incorporate the new diesels do not proposes to determine that the proposed provides for integration of all future significantly alter the accident analysis changes to the Technical Specifications NRC-required work into one in Chapter 14 of the Updated Safety involve no significant hazards comprehensive schedule and has built.m, Analysis Report (USAR). The considerations. mechanisms for changes to the schedule modification of the electrical Loco /Public Document Room when new plant capital modifications distribution system was designed to locotion: Sacramento City-County are identilied or when key program meet single failum criteria and IJbrary,828 i Street, Sacramento, milestones cannot be achieved due to withstand the effects ofload rejection. California 95814. considerations beyond the control of the The system's interaction e"aluation Attorneyforlicensee: David S. licensees. ,
concluded that a failure of one diesel Kaplan, Sacramento Municipal Utility Bosisforproposedno sigmficant generator and associated power District,6201 S Street, P.O. Box 15830, hozords determination:The NRC staff distribution system would not introduce Sacramento, California 95813. proposes to determine that the proposed any unacceptable interactions or any NRCProject Director: John F. Stolz. changes do not involve a significant failures in the remaining electrical hazards consideration because, as distribution with its train. Therefore, this Smithem Califomia Edism Co., et al* required by the criteria of10 CFR change does not increase the probability Docket Nos. 50-361 and 50-362 San 50.92(c), operation of the facility in cr consequences of an accident. Onofre Nuclear Generating Station, accordance with the proposed (2) Create the possibility of a new or Units 2 and 3, San Diego County, CA amendments would not:(1) Involve a different kind of accident from any Dotes of amendment request: August significant increase in the probability or accident previously analyzed. 28 and November 21,1986, consequences of an accident previously implementation of GL 84-15 Description ofomendment request evaluated: or (2) create the possibility of recommendations involves changes ne proposed amendments would add a new or different kind of accident from which demonstrate the operability and new license conditions for San Onofre 2 any accident previously evaluated; or (3) i I
l
assso rederal assister / Vct sz. Ns. rt / Wednesday. Apdl 23,1987 / Notices AttorneyArLicensses. Charles R. Suo to AB mswer Rasctor Moeneses.
involve a alsnl8cantnductionin a Kocher. Beg., Southern Cahfornia Edison %Is clartSostion of the applicability of margin of safety.%e basis for this deRaition 1AC. enly during the Run pedposed findingis given below. Cesapear.2364 Walast Osove Avenue, '
P.O. Box son, ma====ad Cakfornia and Startsp/ Hot Standby modes and the 1.%e proposed chseges establish an 91770 and Orrick.Herrington & SutdlNo. Hot shumleen sendition will not result adadalstrative means for tracidag and Ja anylamense la the probability or scheduling NRC-reguired plant capital ,Atta.: David R.PAgott.Es
das assident previously Montgomery street, san.g.,800 "= --
-adineauons and commitments et the rdsimositismore restrictive and
' California petti. analyse l Econeers.%e Plan does not affect the
- NRChguetMectorr Geospe W. commiseenterisktheassemptions of plant den norNFC ==adated samentanalyses.
=,haa 1== imp 1==antsden of Knighton. _
meancemons.ascean weproposed . venase,m VaasyAdmety,osshoes s.m smenske af d=a-iaa= 1Ac2 are appliasble the Run and heense osaditions fo not afect the plant sees, aDeus,3D.ame and ED.aEE, Amneses Storesp/ Hot and the Hot aseRyretion, r9 anddsat analyses are y,,,yggenges,pisme.Umles1.2 and 3, u===a==.cuency, As, Sheldown esadities willnot ethminate i a5ected;herefore.&e proposed .
er medi$ say preenctive functions. It 1 changes do notincrease the probabGity , Does afasendmentsognet% does notpaumitany asw operational ,
or ooot.squences of anypreviously e,1as7. === dad === lt is essentishy an additional j"
evahasted = arid ==, restrictism.nemisse.1so possibility of 2.no psoposedchanges wiR not alter any asw ar dlSerent kind of accident is i the osmaguration of the plant or its g, m m- - - g g,,,,, esseemd by this ainstSostion. .
therefore,the proposed Ferrytendearfless Undts1.Iand 3. isadest entiesof the do not smontsa new or different 3 af sisRaidos atde ai ea!y Qcade=t frosn any previously est densd6cnwGlasst be he condit onis adednistrative in 1
3.%e proposed changes are .' "Sh'5telowth 1Ms natore lt does esttevolve any seduction administrative and do not afect any clartScadonh unede by &e I accident analyses orinvolve any sentence."IMs k not N6e I"Simme*"I "*'3 " *t **II'for ====d==nt the application modlReation to the plant sooBguration: unitis alreadyinCelsi or thesuitaria for in a of nest ColdButslown or asaspana==a kommeds seasideration safety. admas.1VAhas made a proposed ne t'a==laalan has provided Resis mesgn#foont determinass== that thetipplication guidance sonostnias the application of Jiosois come sisesterinodon Ameniums ao mapan=ne hasards standards for detennining whether a ge r ,=taalonhas provided considerosos.
signiBcant hasards consideration exists standardslor deteredning whether a ne staf has soviewed thelicensee's by providing osrtain swamplas (51 FR sign 1Mcan'.basards deteradnaden exists no W hasants ecosideration of a=and= ants that are as stated into CFR 80AI(c).10 CFR deteradnensa and apons wi& the 7751)dased consi notlikely toinvolve sost roquhos at the tires a liosasse hasmsee's emelysis.herefore, the staff
! significant hasards considerations. . requests an ===ad= pant,it mest provide to es Con ='s==Lon its analyses, proposes to detsrusine that the Frample (i) relates toa purely faramendment involves no administrative changs. for example, a standards latomt,sisout estasse no hasuds esashiersson.
change to achieve consistency signtSonsthasards ='==8d-stion.
throughout the terinical speci$ cations; geregor,,in encantanos wth to CFR Loom /AdecDaoumstrtRoarr lee 881ma* A'b"ma public Ubrary. South correction of an arror, ora changela 30.91 and to CFR anas,the hommene has
=a==nelatore.De proposed change ;, ; -- M and pnyvided the following and Perrest. Athens. Alabanna 38011.
adds a new license condition requiring analysis. Adesnesyjbrboensee General Derw=-a-sa= bas provided Comment.Tummessee Valley Anthority.
' the esiahl'ah= ant and maintenance of The Integrated Uving Schedule Program standards for deterunningwhether a 400 Commmerce Avenue. E 11B 33C.
Plan.The proposed change is Knoxville Teensasse 37902.
strific=it hasards consklerstion edsts NRCAssissantDmsetorforPipfectse J =d=inistrative since thislican= as stated in to CFR anas(c). A proposed condition will require that NRC-required ==and-ant to an operatingliosase ' John A.ZwolinskL
> plant capital =adineaticas and plant involves se sapeaa==t humards UelseEmbleC8mp88y.W No.SS capital medlBcation resultins from BCE ocasiderations tf operation of the faculty ay
"' C"'"'o .riset. Unit s. Callowey
~-
maandtments be traaed and =ehad=1=d in accordsmoswnh to proposed Comey.hd .
Delicense conditionwSInot aHow ====d===t would not ft) tavolve a niptan==e taeresse in the prebebetty or 'Does ofassenenentsequest March 27
&anges to be made to NRC.reguired Implementation dates without rollowing consegesnose of an mockiest .L - L 1887.
Descr$dorrafamenenentsoguese asisting NRC regulations for changes. evolusted.(2) cuentees of a .
Derefore,the proposed change is - new ordiSesamtkled of anddest %slicenses to revise evaluated, or(3) Tednical tioti 5.3.2 to allow for administrative in nature and similar to an accident ,,..L',dmides in a '
the r=g'I======e of a limited number of Ezangde (1)of 81FR 7751. tavelveaalgelSeentse i Beasd as the above,the stsNproposes mar (nofsafety. ' Anal rods with Ruer rods or vacancies if 1.my storifytes that the such. f -t/vecencyis saceptable to deterudne that the proposed changes do not involve a alplRemnt hasards de8alties1ACAage not' provisisms of on to sesidts of the cycle-specific based during Cold Sh=edawa Refuehag, reload anal Also,a sentence which consideration. .
addresses =arimam enrichment of Loon /PW& llc raaer==n' Boom appBcation of A=Anttian 1AC2 is uW-General Library. University of restricted to the spessung osaditions ' the initial core would be deleted.
latended in the modelLCO 3As ResisforpropeesIno sigruficant l Ealifornia at Irvine. Irvine. California hosonir asselderation determination:
m2723, providedby NRC1stter dated AprG10 l
3, , . , - - , - , - - , ,- a w .-g--,, --,--,,,-,-%v w--a -g-, - -- -
Federal Register / Vcl. 52 N:. 77 / Wednesdiy April 22, 1987 / N:tices 18351 The proposed license amendment would Union Electric Co Docket No.50483, localPublic DocumentRoom Callaway Plant, Unit 1 Callaway location: Fulton City Ubrary,700 Market allow the use of filler rods or vacancies Street Fulton, Missouri 85251 and the in fuel assemblies.%ese fuel County, MO Olin Ubrary of Washington University, assemblies willmeet the same Dote ofamendmentrequest: March 27 Skinker and undellBoulevards, St.
mechanical, nuclear, and thermal gge7, Louis, Missour! 63130.
bydraulic limits as an original fuel Description of amendment request:
assembly, se described in FSAR Chapter This amendment application requests Attomerforlicensee: Gerald
- 4. %e reload safety evaluation for each that the applicable modes for Item 6 3 of Charnoff, Esq., Shaw, Pittman, Potts &
Technical SpectScation Table 3.5-3 be Trowbridge,1800 M Street, NW.,
cycle will confirm that the use of a fuel assembly with filler rods or vacancies in clarified regarding the blocking, during Washington, DC 20036.
a core design does not result in an normal plant startups and shutdowns, of NRCPmfectDiivetori B.J.
existing design limit being exceeded. auxiliary feedwater (AFW) start afgnals Youngblood.
Herefore, this license amendment which are automatically generated upon Washinston Public Power Supply request does not involve a significant the trip of both main feedwater pumps. System, Docket No. 56-se7, WNP,2, increase in the probability or %Is clarification would be in the form Richland, WA consequences of an accident previously of a note that would allow the blocking evaluated. of this start signalto the motor. driven Dates of amendment requests: January As discussed above, a fuel assembly AFW pumps just before shutdown of the 6. March 3 and 12,1967.
with filler rods or vacancies satisfies the last operating main ic?dwater pump Description of amendment request:
during plant shutdowns and would his proposed amendment,if approved, same design limits as an original fuel assembly.Therefore, this license require the restmation of this function will change the WNP-2 Technical amendment request does not create the just after the first main feedwater pump Specifiestions by modifying the is placed into service during plant Surveillance Requirements of Section possibility of a new or different kind of startups. 4.1.5. Standby Uquid Control System accident from any acddent previously . .
Bosisforpmposedno significonf (SLCS). Specifically, this change would evaluated. hozords considemtion determination:
As discussed above,the use of a fuel increase the concentration and minimum This change does notinvolve a flow rate of sodiumpentaborate assembly with filler rods or vacancies decahydrate nlution maintained in the wi!! not result in an existing design limit g csfa cci en vi uafy SI. S stwage M being exceeded. Therefore, this change evaluated. No credit is taken for this does not reduce the margin of safety. start signalin the accident analyses ne regulatipo for ATWS mitigation (10 CFR 50.62(c)(41) requires that the The Commission has provided certain which assume that AFW actuation is SLC System have a minimum flow examples (51 FR 7744) of actions likely generated by the low. low steam capacity and boron content equivalent to involve no significant hazards generator water level signal.This in cetrol capaci to 86 gallons per considerations. Example (i) relates to a change has no effect on this or other minute of 13 weig t percent sodium purely administrative change to the start signals (i.e., safety injection signal, Pentaborate solution.%e present technical specifications.He loss of offsite power) which remain specification requires a minimum flow amendment would also delete a available to respond to accident rate of 41.2 gallons per minute and a sentence which addresses the maximum situations.The use of the block switches minimum concentration of134 percent.
enrichment of the initial core.%1s precludes the undesired ESF actuation Accordingly, Sectim 4.1.5 of the WNP-2 sentence is historical and has no curr during plant startups and shutdowns Technical Specifications must be applicabiliiy and therefore represents a. under conditions where the motor. changed to comply with the regulation.
purely administrative change. driven startup feedwater pump provides ne SLC System design modification Based on the above discussions, the the necessary feedtvater source.
This change does not create the at,WNIL2 will result in anincreased amendment request does not involve a injection rate by simultaneous operation significant increase in the probability or possibility of a new or different kind of of both SLCS pumps.ne minimum consequences of an accident previously accident from any accident previously evaluated. This is based on the fact that sodium pentaborate concentration will evaluated; nor create the possibility of a also be increased to 13.6 weight percent.
the method and manner of plant new or different kind of accident from operation is being clarified to achieve The higher concentration levels are any accident previously evaluated; nor necessary to meet the equivalency involve a reduction in the required consistency with those documents requirements at the minimum flow rate margin of safety. Based on the foregoing, establishing the licensing bases for the presently required by the Technical the Commission has determined that the Callaway Plant (i.e., NUREG-0830. SER Specifications for each of the two related to the operation of the Callaway reonested amendment does not involve pumps.
Plant. Section 7.3.2.7 and FSAR Sections a significant hazards consideration. . 6.1.1 a,15.2.6, and 15.2.7).
Bosis forproposedno signifi LocalPublic Document Room This change does not involve a hozords considemtion determm} otion: con,t Iocation/ Fulton City Library,709 Market significant reduction in a margin of The proposed amendment to the WNP-2 Street, Fulton. Missouri 65251 and the safety.This is based on the fact that no Technical Specification to require Olin Library of Washington University, design changes are involved and the conformance with the Regulation is Skinker and Lindell Boulevards St. change to clarify mode applicability is similar to Example (vil) provided by the kuis, Missouri 6313& consistent with the sta!!'s safety Commission (51 FR 7751. March 6,1986)
Attorneyforlicensee/ Gerald evaluation of the auxiliary feedwater of the types of amendment not likely to Charnoft Esq Shaw,Pittman, Potts & system actuation design. involve significant bazards Trowbridge 1800 M Street NW., , Based on the above information, the consideration. Example (vii) denotes an Washington.DC 20036. Commission has determined that the amendment to make a license conform NRCPmject Director:B.J. proposed amendment involves no to changes % the regulation when the Youngblood. significant hazards consideration. license change results in very minor I
i
13352 Federal Register / Vcl. 52. No. 77 / Wedneedsy. April 22, 1987 / Notices Washington PublicPower Supply Technical Specifications and regulations changes to facility operations clearly in System. Docket No.88 497,WNP-2, are not significantly changed; and
. keeping with the regulations.
miAlaad WA (4) %e NRC has previously found in addition.the Commission has such methods acceptable, pmvided standards for detenining Date afomendment request: March 27 whether no significant hasards This reload will consist of 764 1987 assemblies, approximately ese of which consideration exists (to CFR 50.92(c)). A D$scription ofomendment request: are twice burned (two operating cycles) proposed amendment to an operating De proposed amendment would revise h.eense for a facility involves no the WNP-2 Technical Specifications GE fuel assemblies.128 of which are significant hasards consideration if (TS) to support the operation of WNP-2 once burned Exxon fuel assemblies and approximately les of which are new operation of the facility in accordance at full rated power during the upcoming with the proposed amendment would Cycle 3.ne proposed amendment ANF fuel assemblies.The ANF fuel assemblies are very similar to the Exxon not:(1) Involve a significant increase in request to support this reload changes and the GE fuel assemblies except for the probability or consequences of an the Technical Specifications in the slight differences in the mechanical, accident previously evaluated; or (2) following areas:(1) Establishes thermal. hydraulic and nuclear design.
create the possibility of a new or operating limits for all fuel types for the
. Although the ANF fuelis very similar different '.ind of accident from an upcoming Cycle 3 operation:(2) reflects to the existing fuel, the slight differences -
accident previously evaluated; or (3) the replacement of approximately 148 in mechanical, thermal-hydraulic and involve a rignificant reduction in a initial core fuel assemblies with nuclear design of the bundles, and the .
margin of afety.
Delicensee has determined, and the AdvancedNuclearFuels(ANF)
Corporation fuel assemblies for t heuse of different analysis methodologies, required thet a wide range of reenalyses staff agrees. that the requested upcoming Cycle 3 operation: and (3) be performed by ANF Corporation.
amendment per to CFR 50.92 does not: modifies the Bases section of the Rose reanalyses included reanalyzing
. (1)lavolve a significant increase in Technical Specifications to account for for anticipated operational occurrences, the probability or consequences of an the use of ANF fuel assemblies. performing LOCA analyses for the ANF amident previously evaluated because To support the license amendment fuel and analyzing for the rapid drop of l the SIES sodium pentaborate solution reques'. for operation o(WNP-2 during concentration and Row rate required by a high worth control rod to assure that Cycle 3. the Supply System submitted, I
as attachments to the application the excessive energy will not be
- deposited j the NRC for reactivity control in the fuel Analyses for normal l ladependent of the control rods exceed following:
the values previously presented in the Operation of the mactor maalated of fuel Technical Specification and the change L WNP-2 Cycle 3 Reload Summa 7udes evaluations in the areeg of mechanical, Report (WPPSS-EANF-100)Inc thermal. hydraulic and nuclear design.
does not affect the possibility of an the Startup Physics Test Program
. The use of the ANF type fuel ATWS. II.WNP-2 Cycle 3 Reload Analysis (2) Create the possibility of a new or assemblies and the associated (XN-NF-47-25) analytical methods used for the Cycle 3 -
different kind of accident than III.WNP-2 Cycle 3 Plant Transient Analysis (XN-NF-47-24) reload analyses have been previously previously evaluated because the IV.WNP-2IDCA-ECCS Analysis approved by the NRC staff for use in increase in the SLCS tank solution flow other boiling water reactors (BWR's).
rate and concentration provide MAPtJIGR Results (XN-NF-8b13e) sufficient boron to achieve a cold plant V. Technical SpecL6 cation Changes Based on these prior reviews, the NRC staff has determined that there are only shutdown and the temperature limits are During the second refuel' outage adjusted to accommodate the maximum approximately 148 General tric (GE) small ANF and differences between GE analytical the use of methods.
allowable concentrations so as to initial fuel assemblies (approximately one fifth of the core) will be replaced his core reload involves the use of Preclude solute precipitation. fuel assemblies that are not significantly (3) Involve a significant reduction in a with new, but substantially similar, different from those found previously margin of safety because, over the entire ANF. Type ANF(8xecbundles.2.72 acceptable to the Commission for a range of permissible tank volumes. (weight) percent enrichment). fuel assemblies. previous core at this facility.The higher minimum SLCS tank solution .
concentration actually increases the Bosisforproposedno significant proposed amendment would change the .
Technical Specifications to reflect new boron available to achieve a cold horoids consideration determination:
shutdown and the rete ofits addition The proposed amendment to the WNP-2 operating limits associated with the fuel has been increased also increasing the Technical Specifications to support this to be inserted into the core based on the reload is very similar to Example (iii) new core physics and are within the margin of safety. acceptance criteria. In the analyses Based on the above considerations. provided by the Commission (51 FR 7751. March 6.19e6) of the types of supporting this reload, there have been the Commission proposes to determine no significant changes in acceptance that the requested change to the WNP-2 amendments not likely to involve criteria for the Technical Specifications Technical Specifications involves no significant hazards considerations. ,
Example (iii) is an amendment to reflect and those analytical methods used have significant hazards considerations- previously been found acceptable by the LocolpublicDocument Room a core reload where:
location: Richland Public Library. Swift (1) No fuel assemblies significantly NRC.
different from those found previously The only difference between this .
and Northgate Streets.Richland. reload and Example (iii) provided by the Washington 99352. acceptable to the Commission for a previous core at the facility in question NRC is related to the use of the ANF ~
Attorneyfor the Licensee: Nicholas analytical methods which are slightly Reynolds. Esquire. Bishop. Liberman, are involved:
Cook.Purcell and Reynolds.1200 (2) No significant changes are made to different from the GE methods used for Seventeenth Street NW. Washington. the acceptance criteria for the Technical Cycle 1 and the Exxon (now ANF)
Specifications: .
methods used for Cycle 2.The ANF DC 20036. analytical results are not significantly NRCProject Director:Elinor G. (3)ne analyticalmethods used to demonstrate conformance with the different from those previously found Adensam.
Federal Register / Val. 52. N . 77 / Wednesday, April 22, tetr7 / Notices 18358 l 1
acceptable to the NRC for the previous Seventeenth Street NW., Washington. Wlaaa-la Electric Power Co., Docket coree at WNp-2 and the methods DC 20036. Nos, so-ass and 86-301, Point Beach previously have been approved by the NRCProjectDimetor:E. Adensam. Nuclear Plaats Unit Nas.1 and 2. Town staff for use in other BWR's. of Two Creeks,Manitowoc County,WI In addition to providing examples of Wlacocain Electric Power Co., Dockat Nos.36-ass and 56 301 Point Beach Date of amendments request: January amendments not likely to involve a significant hazards consideration, the Nuclear Plants, Unit Nos.1 and 2. Town 8.1987.
Commission has provided standards for of Two Creeks,Manitowoc County,WI Description of amendments request determining whether no significant The proposed amendments would hf amendments aquest: January modify the Technical Specifications to hazards consideration exists (10 CFR 8* 1887*
50.92(c)). A proposed amendment to an ,
change the number of channels listed in operating license for a facility involves De8Cription of amendments request: Table 15.3.5-4. Item 10. " Containment no significant hazards consideration if The proposed change to the Technical Hydrogen Monitors" from four to two.
operation of the facility in accordance Specifications (TS) would provide ne proposed amendments would also with the proposed amendment would clarification in the remarks column of correct an error in Table 15.3.5-2.
not:(1) Involve a significant increase in Table 15.4.1-1 concerning the frequency " Instrument Operation Conditions for the probability of consequences of an for conduct of reactor coolant flow logic Reactor Trip." The change would accident previously evaluated; or (2) channel testing. Specifically, logic correctly indicate that for the low flow
. create the possibility of a new or channel testing forloss of coolant flow (both loops) trip the number of channels different kind of accident from an in both loops shall be tested each to trip is 2/ loop (both loops) instead of accident previously evaluated; or (3) refueling interval. / 2/ loop (any loop) as is currently involve a significant reduction in a Basisforpmposedno significant indicated. He change would also clarify margin of safety. hozonis considention detenninotion: that the minimum operable channels On the basis of the evaluation The licensee has performed analysis in and mmimum degree of redundancy accordance with the standards of10 figures for the low flow trip are "per
. nd e fac a e al ti CFR 50.92 to determine if the proposed loop
- figures.
methods used have been approved Lastly, the proposeql amendments previously by the NRC staff and do not change involves any significant hazards considerations.The licensee states that would change the tann "zero power provide results significantly different, physics testing" to " low power physics the Supply System has concluded, and the proposed change provides clarification with respect to the testing"in the footnote foritem 2 of the staff agrees, that operation of WNP-2 in accordance with the proposed conditions necessary for performance of Table 15.3.5-2 a,d modify the wording a portion of a surveillance requirement of the set points for items 9.10s and 10b reload amendment would not:(1) of Table 15.3.5-1 to eliminate ambiguity.
involve a significant increase in the and, therefore, would not increase the probability or consequences of an probability or consequences of a Basisforproposedno significont accident previously evaluated because previously evaluated accident. hozoids considemtion determinatioa:
the proposed changes to the Technical Secondly, the change involves no The licensee has evaluated the proposed Specifications reflect new operating physical or pmcedural changes to the Technical Specification change request limits associated with the fuel to be plant and. therefore, would not create with respect to the criteria of to CFR inserted in the core and which are based the possibility of a new or different kind 50.92 and has determined that the on reanalyses using the new core of accident from those previously proposed amendments would not result physics with results that remain within evaluated. Lastly, the licensee states in a significant hazards consideration.
the previously accepted operating limits: that the proposed change would not ne licensee has indicated that the or (2J create the possibhy of a new or involve a significant reduction iny proposed amendments are largely different kind of accident from any administrative in nature and are not the margin of safety because the ch""8e accident previously evaluated because resuit of plant modifications or the ANF fuel technology and the design clarifies the operational conditions necessary to perform that portion of the procedural changes; and would thus not of the fuelis not significantly different create the possibility of a new or surveillance requirement which would from that used in the previous cores not result in any reduction of a safety d e t f accide r n which were found acceptable to the , dent NRC staff: or (3) involve a significant margm. because the proposed amendments are reduction in the margin of safety The staff has reviewed the licensee's " & ul ph 1 1 because the margin of safety for all analysis and concurs with their findings. ch es. e ill n in as e accidents or operational occurrences The staff, therefore, proposes to pmb bility o co se e ces an analyzed for Cycle 3 operation is either determine that the amendments would cid identical to or more conservative than involve no significant hazards Lastly, while the amendments propose that used for Cycle 2. considerations
- a reduction in the number of hydrogen Based on the above considerations. LocoIPublic Document Room monitor channels requred by the the Commission proposes to determine locadondoseph P.Mann Library.1516 Technical Specifications, the proposed that the requested change to the WNp-2 Sixteenth Street.Two Rivers, Technical Specifications involves no nu.nber of channels still meets the staff Wisconsm. Euldance as contained in Generic letter significant hazards considerations. 83-37 and, therefore. would not Attorneyforb.censee: Gerald LocalPublicDocument Room Chamoff. Esq., Shaw. Pittman, potts and constitute a significant reduction in a location: Richland Public Library. Swift and Northgate Streets.Richland. Trowbridge,2300 N Street NW., margin of safety.The remaining changes Waslungton 99352. . Washington DC 20037. being administrative (correcting erre-s Attorneyfor the Liceasee: Nicholas NRCProjectDirector George E. lear. or clanfymg language to reduce Reynolds. Esquire. Bishop. Liberman, ambiguity) cannot affect the margin of Cook, purcell and Reynolds.1200 safety. l l
1
, 13354 Federal Eagleter / Vcl. S2, No. 77 / W:dneedsy, April 22, 1887 / Notic s
.%e staff has reviewed the licensee > for the particular facilities involved. A the license for Unit 1 and the Technical copy ofitems (2) and (3) may be Specifications for both Unit 1 and Unit 2.
! determination and concurs with their
' findings.nerefore, the staff proposes to obtained upon request addressed to the Date ofinitio/noticein the Federal r determine that the proposed U.S. Nuclear Regulatory Commission, Register: February 11.1987 (52 FR 4402).
a amendments involve no significant Washington, DC 20555, Attention: r De 'annadaaion's related evaluation i hazards consideration. Director, Division of Ucensing. of the amendments is contained in a .
LocalPublic Document Room Safety Evaluation dated April 8,1987.
- '
- No signincant hazards consideretion r I location: Joseph P. Mann Ubrary,1518 N l'N M Sixteenth Street.Two Rivers, ggg, pg ym g, -n==nts were received: No.
m A r yforlimnsee:Cerold Station, Units 1 and 2 Marleepe County, . [gni ,
Charnoff. Esq., Shaw, Pittman. Potts and AZ Bosiness, Science and Technology Trcwbridge,2300 N Street, NW., Date of applicationforamendments: Department 12EastMcDowellRoad.
Washmgton, DC 20037. July 14.1988, as supplemented by letters PhoeMx, Arizona 85004.
NRCrioject Director: George E. Imar. dated December 2.1988, and February 9,
, Carollma Power & Ught Co., Dockets -
1987 i
NOTICE OFISSUANCEOF Briefdescription of amendments:De Nos.38-833 and sm Smaswick l AMENDMENTTO FACIUTY Mmenu delew ophin acuons of Steam Electric Plant. Units 1 and 2, t 1
OPERATING UCENSE the Technical Specificadons pertaining Brunswick Ceesty.NC , ,
i During the period since publication of to the fire protection program, since the Date ofopplication foromendments:
the last bi-weekly notice, the program is currently in the FSAR. A August 7.1985 Commission has issued the followin8 change is also made to the Unit 11icense Relefdescription of amendments:De
- amendments.ne Commission has concerning the fire protection program. Unit 1 amendment correc's a determmed for each of these Date ofissuance
- April 8,1987. typographical error in the Unit 1 Facility amendments that the application Effective dote: April 8,1987, to be Operating Ucense.The Unit 21icense is complies with the standards and implemented within 30 days of issuana. amended to be consistent with the Unit requirements of the Atomic Energy Act Amendment Nos.:14 and 8.
Focility Operating License Noe.: NPF-I 1;*** I """ "8 "'W" *" bI of1954, as amended (the Act), and the Commission's rules and regulations.%e 42 andNPF-51: Amendments revised C. W urce PeciaMar t 28 8 #88 or 8 amp l e analysis r
- Commission has made appropriate the license for Unit 1 and the Technical . "' '
findings as required by the Act and the Specifications for both Unit 1 and Unit 2. Nth osctive apparptus or .
j Commission's rules and regulations in 10 Date offhitiolnoticein the Federal ""
pter ch are set forth in the . December 30,1988 (51 FR Do ce. March 31,1987.
j
- fecdve date arch 31,1987.
I Notice of Consideration ofissuance of The Commission's related evaluation Amendments Nos.:105 and135. ,
Amendment to Facility Operating of the amendments is contained in a . FocMy Opemung Limnses Nm.
{ Ucense and Proposed No Significant Safety Evaluation dated April 8,1987. DPR-71andDPR-42. Amendment ;
Hazards Consideration Determination No significant hazards consideration
! mvised the Hcems. . ;
and Opportunity for Hearingin comments were received: No.
1 connection with these actions was Loco 1PublicDocumentRoom Date ofinitiolnoticein Federal j Register: Octobet 9,1985 (50 FR 41243).
published in the Federal Register as location: Phoenix Public Ubrary, indicated. No request for a hearing or Business. Science and Technology The Commission's alakd mluation
] Department.12 East McDowellRoad. of the amendment is contained in a i petition for leave to intervene was filed Safety Evaluation dated March 31.1987. f i following this notice. Phoenix, Arizona 8500s. '
- Unless otherwise indicated, the No signiBeant hazards consideration Artsome Pubuc Servios y, et al. . comments received
- No.
Commission has determined that these STN 88-4 amendments satisfy the criteria for Docket Nos.STN 58-838 Loco 17tsblic Document Room 839, Palo Verde Nuclear Generating -location: University of North Carolina at i categorical exclusion in accordance with 10 CFR 51.22.nerefore, pursuant Station, Units 1 and 3. Maricopa County, Wilmmston, William Madison Randall to 10 CFR 51.22(b). no environmental AZ Ubrary,801 S. College Road, impact etatement or environmental Date of applicationforamendments: Waa"-a'aa. North Carolina 28403-3297.
assessment need be prepared for these January 19,1987. Camuna Power and Ught Co., Docket
- amendments.If the Commission has Snefdescription ofomendments:The No.58-381.H.B. Robinson Staam
, prepared an environmental assessment amendments revise the Technical Electric Plant, Unit No. 2 Darlington Specifications to remove Main Steam '*
' under the special circumstances County, SC provisionin10 CFR 51.12(b) and has isolation Valves (MSIVs) from the list of valves that are subjected to the Date of applicationforomendment: .
made a determination based on that December 18,1986.
' assessment,it is so indicated. requirements of Specincation 3/4.8.3,
- For further details with respect to the " Containment Isolation Valves " since Briefdescription of amendment:The action see (1) the applications for another Specincation 3/4.7.1.5," Main amendment revises the Technical
! Specifications by replacing the existing .
] amendments.(2) the amendments,and Steam Une Isolation Valves,"
(3) the Commission's related letters, specifically provides the operability and heatup and cooldown curves in Figures surveillance requirements for the 3.1-1 and 3.1-2, respectively, with two Safety Evaluations and/or sets of curves.He replacement curves Environmental Assessments as MSIVs.
Date ofissuance: April 8,1987. are applicable for up to 12.5 and 15 indicated. Allof theseitems are - effective full power years (EFPY),
available for public inspection at the Effective date: April 8,1987.
Amendment Nos.:15 and 9. respectively.
Commission's Public Document Room. Date ofissuance: March 31,1987.
( 1717 H Street NW Washington, DC, Facility Operating License Nos.:NPF-~
and at the local public document rooma di andNPF-41: Amendments avised Effective date: March 31,1987.
l i
- - - ~~--------e--.m,.- .~-- .-,--.%- .--w,..-,v,-,-.e----c.m -...._4- -m.r- .., ,- r.-- - - - , - - - - - - - ----m-- --
Federal Regleter / Vgl. 52 No. 77 / Wedneeday, April 22,1D / Notices 13855 Amendment No.113. (1) new reporting requiremente of to Facility Openting Ucense Nos. NPT-Farility Opemting Ucense No.DPR- CFR 50.73 and (2) addition of detells to 35 andNPF-32. Amendments revised
- 23. Amendment revised the Technical the requirements of the reports for diesel the Technical Specifications.
Specifications. generator failures. Date ofinitiolnoticein Federal Date ofinitialnoticein Federal DateofIssuance April 8,1987, Register: February 28,1987 (52 FR 5852).
Register: February 28,1987 (52 FR 5851). Effective date: April 8,1987, The Commission's related evaluation of he Commission's related evaluation of Amendment No.155. the amendments is contained in a Safety the amendment is contained in a Safety PmvisionalOpemting Ucense No; Evaluation dated Aprill,1987.
Evaluation dated March 31,1987. DPR-45. Amendment revised the No significant hazards consideration No significant hazards consideration Technical Specifications. comments received: No.
comments receised: No. Date ofinitialnoticein Federal LocalPublic Document Room LocalPublicDocumentRoom Register. June 20,1984 (49 FR 25358): location: York County Libruy,130 East location: Hartsville Memorial Library, October 24,1984 (49 FR 42818). Black Street, Rock Hill. South Carolina Home and Fifth Avenues. Hartsville, The Commission's related evaluation 29730.
South Carolina 29535' for the license amendment is contained
. in a Safety Evaluation dated April 8. Duke Power Co., et al, Docket Nos. 50-Commonwealth Edison Co., Docket No. 413 and 50-414, Catawba Nuclear 1987 30-237 Dresden Nuclear Power Station. No significant hazards consideration Station, Units 1 and 2. York County, SC Unit No.2, Grundy Co tnty,IL comments received: No.
Date of applicationforamendments:
Date of applicationfaramendment: LocalPublic DocumentRoom July 31.1985, ae supplemented December 10,1988, as supplemented location: La Crosse Public Library,800 November 8,1985. March 7 and October January 28 and February 5,1987. Main Street, La Crosse, Wisconsin 1 and 10,1988.
Briefdescription ofamendment:This $4801. Briefdescription of amendment.c The amendment changes the Dresden 2 Duke Power Co., et al Docket Nos. 50 amendments modify Technical License and Technical Specifica3ons to 413 and 50-414, Catawba Nuclear Specifications 8.5,8.6,8.8 and 8.10 support Cycle 11 operation. regardmg " Administrative Controls."
Station Units 1 and 2. York County,SC Date ofissuance: March 31,1V7. Date ofissuance: A ril 2.1987.
Effective date: March 31,1987. Date of applicationforamendments: Effective date: Apri 2.1987.
Amendment No. 95. December 13,1985.
PmvisionalOpenting License No. Amendment Nos.:27 Bnefdescription of amendments:%e FacHRy Opemungh.and 17*
DPR-19. The amendment revised the amendments change the Technical cense NosM-license and the Technical Specifications. Spedfications related to reportbg 35andNPF-52. Amendments revised the Technical Specifications.
Date ofinitialnoticein Federal requirements for primary coolant iodine Resister: January 28,1987 (52 Fi' 2878); spikes, and delete existing shutdown Date ofiniuolmucein Federal February 8,1987 (52 FR 3894). In the Register: February 28,1987 (52 FR 5852).
requirements if coolant !odine activity February 5,1987 letter Commonwealth The Commission's related evaluation of limits are =xceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12 Ediscn requested. pursuant to to CFR month period. the amendments is contained in a Safety 2.107, permission to withdraw that Evaluation dated April 2,1987.
Date ofissuance: A ril1,1987.
portion ofits previous amendment Effective date: Aprif1,1987. No significant hazards consideration request which originally proposed a Amendment Nos.:25 and 15. comments received: No.
Minimurn Critical Power Ratio (MCPR) Facility Openting License Nos.NPF- . LocalPublicDocumentRoom safety limit of1.05. Commonwealth 35cndNPF-52, Amendments revised eocation: York County Library,138 East Edison agrees to continue to use the the Technical Specifications. Black Street, Rock Hill, South Carolina existing MCPR limit of 1.08 for residual 29730.
Date ofinitialnoticein Federal 8x8R General Electric fuelin the Register: August 27,1988 (P. FR 30585). Florida Power Corp., et al, Docket No.
Dresden Unit 2 Cycle 11 Reload.%e The Commission's related eva;uation of 50-302, Crystal River Unit No. 3 N=laar U.S. Nuclear Regulatory Commission the amendments is contained in a Safety Generating Plant Citrus County, FL has granted the request of Evaluation dated April 1,1987.
Commonwealth Edison to withdraw this No significant hazards consideration Date of applicationforamendment:
portion of its December 10,1988 comments received: No. February 17,1988, as supplemented application. LocalPublicDocumentRoom November 19 and 25,1988, and February The Commission's related evaluation location: York County Library 138 East 17'1987-of the amendment is contained in a Black Street. Rock Hill, South Carolina Briefdescription of amendment:%e Safety Evaluation dated March 31,1987. 20730. amendment changed the expiration date No significant hazards consideration for Facility Operating License No. DpR-Duke Power Co., et al., Docket Nos 50- 72 from September 25,2006 to December comments received: No. 413 and 50-414, Catawba Nuclear LocalPublic DocumentRoom 3,2018,40 years from the issuance of the location:Ltorris Public Library,804 Station, Units 1 and 2. York County, SC operating license.
Liberty Street Morris, Illinois 80450. Date of applicationforamendments: Date ofissuance: March 31,1987.
July 31.1985, as supplemented October Effective date: March St.1987 Dalryland Power Cooperative, Docket 10,1988. Amendment No. 97.
No. 50-409, La Crosse Boiling Water Briefdescription of amendments:%e Facility Opemting License No. DPR-Reactor, Vemon County, W1 amendments would modify Technical 72. Amendment revised the operating Date ofapplicationforamendment: Specification Surveillance Requirement license.
March 20,1984 as amended August 24. (4.8.2.1.ta.3) to allow battery operation Date ofinitialnoticein Federal 1984. when there is minor electrolyta leakage. Register: October 8,1988 (51 FR 38090).
Briefdescription of amendment:The Date ofissuance: April 1,1987. Since the date of the initial notice, the amendment authorizes changes to the Effective date: April 1,1987. licensee submitted clarifying Technical Specifications pertaining to Amendment Nos. 28 and 18. information dated November 19 and 25, I
i 13356 Federal Regist:r / Vcl. 52. No. 77 / Wrdnesday. April 22, 1987 / Notices 1986, and Febiuary 17,1987. His surveillance requirements were Date ofinitiolnoticein Federal information did not change the original included. Register: February 26.1987 (52 HL 5856) apphcation in any way and, therefore. Date of/ssuance: April 7;1987. He Commission's related evaluation of did not warrant renoticing. Effective Date: April 7.1987. the amendment is contained in a Safety The Commission's related evaluation Amendment Nos. 79 and 19. Evaluation dated March 31.1987.
of the amendment is contained in an Facility Opemting License Nos. DPR- No significant hazards consideration Environmental Assessment dated March 67andNPP-Jo: Amendments revised comments received: No.
26.1987, and a Safety Evaluation dated the Technical Specifications. LocoIPublic Document Room March 31.1987 Date ofinitialnoticein Federal location: Government Publications No significant hazards consideration Register: September 11.1985 (50 FR Section. State Library of Pennsylvania, comments received: No. 37073 at 37082). Education Building. Commonwealth and LocalPublic Document Room %e Commission's related evaluation Walnut Streets. Harrisburg.
Location: Crystal River Public Library, of the amendments is contained in a Pennsylvania 17126.
668 N.W. First Avenue. Crystal River. Safety Evaluation dated April 7.1987.
No significant hazards consideration Indiana and Michigan Electnc Co, Florida 32629* Docket Nos. 50-315 and 56-318. Donald comments received: No.
Florida Power Corp, et al. Docket No. LocalPublic Document Room C. Cook Nuclear Plant. Unit Nos.1 and 50-302. Crystal River Unit No. 3 Nuclear lomtion: Indian River junior College 2. Berrien County, MI Generating Plant. Citrus County. Fl. Library.3209 Virgina Avenue.Ft. Pierce. Date of application foramendments: -
Date of applicationforamendment: Florida 33450. November 13.1986.
September 2.1986, as supplemented Georgia Power Co,palethorpe Power Briefdescription of amendments:He January 15.1987. Corp., Municipal Electric Authority of amendments change the Technical Briefdescription of amendment:The Georgia. City of Dalton, GA. Docket No. Specifications to clarify that Section 3/
cmendment relaxes action statements 4.4.5 allows crevice flushing of steam 56 321. Edwin L Hatch Nwlaar Plant.
for Technical Specification (TS) 3.8.1.1 Unit No.1. Appling Count GA generators in Mode 4.nis is a partial in order to increase diesel generator approval of the licer.see's proposed reliability. A supplemental submittal on Date of applicationforamendment- amendment to charge the overall intent September 9.1986 from operable to integrity, January 15.1987 made clarifications in Briefdesenptwn of amendment:%e This amendment also changes Table the Bases of the TS. u of am m es 4.4-1. footnote 2. to require second and Date ofissuance: April 7.1987.
Effective date: April 7.1967. subsequent inspections en one steam requirements to clarify them. generstor during each inspection.
, Amendment No.:98. " *
- Facility Openting License No. DPR- Dateofissuance: April 1.1987.
fe*c v daMYa 1Y7 EUective date: April 1.1987.
- 72. Amendment revised the Technical Amendment No.:135.
Spec 1tications. Facility Opemting License No. DPR- Amendment Nos.:103 and 89.
Date ofinitialnoticein Federal Facility Opemting Ucense Nos. DPR-
- 57. Amendment revised the Technical Register: November 19,1980 (51 FR Specifications. Se andDPR-74. Amendments revised 41854).The Commission's related the Technical Specifications.
Date ofinitialnotice in Federal evaluation of the amendment is Register: February 26,1987 (52 FR 5855). Date ofinitialnotice in Federal contamed in a Safety Evaluation dated The Commission's related evaluation Register: December 17.1986 (51 FR April 7.1987. of the amendment is contained in a 45203) The Commission's related No significant hazards consideration Safety Evaluation dated March 31.1987. evaluation of the amendments is comments received: No. No significant hazards musideration contained in a Safety Evaluation dated LocalPublic DocumentRoom comments received: No. April 1.1987.
Location: Crystal River Public Library. localPublic DocumentRoom No significant hazards consideration 668 N.W. First Avenue. Crystal River. Location: Appling County Public comments received: No.
Florida 32629. Libre ry. 301 City Hall Drive. Baxley. LocalPublic Document Room Georgia. lomtion:Maude Preston Palenske Florida Power and Light Co, et al., * '
Docket Nos. 50-335 and 50-389, St. Lucie GPU Nuclear Corp, et al., Docket No. J eph. g 49085-Plant. Unit Nos.1 and 2. SL Lucie 50-289, Three Mile Island Nuclear County. FL Station. Unit No.1. Dauphin County. PA Indiana and Michigan Electric Co,
'y N**{
Date of application of amendments: Date of applicationforamendment: y, y July 19,1985. Janus 28,1987. 2. Begen County, M1 Brief description of amendments: Tbe Bri description af amendment:%is amendment for the St. Lucie Plant. Unit amen ment prescribes additional fire Date of applicationfor amendments: .
No.1 revised the technical detection and suppression operability August 19.1986 specifications to add Incore requirements that encompass the fire Brief description of amendments: The Thermocouples. Containment Sump protection modifications accomplished amendments would change the Water level (narrow and wide ranges), during the 6R outage as part of the Technical Specifications on snubbers to -
Containment Pressure, and Reactor commitments to satisfy 10 CFR Part 50. correct a number of errors. and to allow Vessel Level Monitoring System to Appendix R. surveillance inspections to be performed Tables 3.3-11 and 4.3-7. The amendment Date ofissuance March 31.1967. sooner.He change to clarify that the i
for St. Lucie Plant, Unit No. 2 revised the Effective date: March 31.1987 fluid observation port at the entreace to
! technical specifications to add the Amendment No.127. Be valve operator must be checked and Reactor Vessel level Monitoring System facility Opemting License No. DPR- full to have an operable snubber was to Tables 3.3-10 and 4.3-7. Appropriate 50. Amendment revised the Technical deleted and agreed to by the licensee.
operability and actions statements and Specifications. Date ofissuance: April 7.1987.
Federal Regleter / Vrl, 52, No. 77 / Wednesday, April 22, 1987 / Nitices 13337 Effective date: April 7,1987. Facl/ity Operet/ng ucense No. NPF- requirements for mechanical snubber Amendment Noe.:104 and 91. 38. Amendment tevised the Technical operability and testing.
Facility Operating license Nos. DPR- Specillcations. Date ofissuonoe: April s,1987' 58 andDPR-74. Amendments revised Dat6s ofin/t/alnot/ce in Federal the Technical Specifications. .Kffective Date: April 3'1987*
Register: December 17,1986 (51 FR Date ofinitialnoticein Federal 45208). Amendment No.:96.
Register. September 24,1986 (51 FR The Commission's related evaluation facility Operat/ng License Na DPR-33951). of the amendment is contained in a 38: Amendment revised the Technical The Commission's related evaluation Safety Evaluation dated April 3,1987. Specifications.
of the amendments is contained in a No significant hazards consideration Date ofin/flalnotice in Federal Safety Evaluation dated April 7,1987, comments received: No. Register: June 20,1984 (49 FR 25363 and No significant hazards consideration LocalPublicDocument Room November'19,1986 (51 FR 41843 at comments received: No. location: University of New Orleans LocalPublicDocumentRoom Library, Louisiana Collection Lakefront, 41863)~
j location: Maude Preston Palenske New Orleans, Louisiana 70122. %e Commisalon's related evaluation -
Memorial Library, 500 Market Street, St.' *** " " ' " * " ' I*
Maine Yankee Atomic Power Co., Safety Eva untion dated April 3,"1987.
Joseph. Michigan 49085. Docket No.56-300. Maine Yankee Atomic Power Station, uncoln County, t haza a consideration Indiana and Michigan Electric Co, sI{lf Docket No. 50-315, Donald C. Cook ME Nuclar Plant, Unit No.1, Berrien Date of applicationforamendment: LocalPublic Document Room County, MI October 7,1982. April 13,1984, and location: Wiscasset Public IJbrary. High Date of applicationforamendment March 4,1985,, cl,arified April 26,1985. Street,Wiscasset Maine.
- M' " ' ' * * *k *
- B i f est p n of amendment:%e Energy Resources.Inc., South' Y amendment revises the Technical Technical Specifications (TS) such that the areas of the TS concerning Mississippi Electric Po,wer Association, operability and surveillance for new Docket No. 50-418, Grand Gulf Nuclear I o to re h i b verified once p r hour for twelve hours a ble gas effluent monitors, high range Station, Unit 1, r%1harne County, MI or until verifie acce table at 95% or ra n mo tors and wa rlevel
, Date of appliegtionforamendment:
8" October 17,1986.
simplified.The areas of the TS e f[ssua[c7A 7,i987, concerning surveillance requirements Briefdescriptw, n of amendment:The Effective date: April 7,1987.
Amendment No.: m5. f r Containment Pressure Monitors were proposed amendment would change the facility Opemting License Na DPR- changed to reflect certain aspects of Technical Specifications (TSs) by: (1)
NUREG-0737. In addition, the entire Deleting the two-minute time limit for
- 58. Amendment revised the Technical Specifications. Section 3.9 of the TS was rewritten to closing a stuck open safety relief valve reflect an overall simplification of (SRV) and changing the temperature Date ofinitialnoticein Federal language, Register: January 14,1987(52 FR 1555) limit of the suppression pool water from
&te ofissuance: March 26,1987. 105* to 110 *F; (2) adding a requirement The Commission's related evaluation of Effective D te March 26,1987.
the amendment is contained in a Safety to bypass the thermal overload Evaluation dated April 7,1987. protection device for the motor operated No significant hazards consideration fac ty E /.icenseNa DPR- valve in the nactor core isolauen 36: Amendment revised the Technical comments received: No. co ling (RCIC) turbine bypass line: and LocalPublic Document Room location:Maude Preston Palenske SE*ifications' Date ofinitia lnotice in Federal(3) changing the nomenclature of a Register: July 20,1983 ($8 FR 33082): June secondary containment isolation valve Memorial Library,500 Market Street St. 20.1984 (49 FR 25363) and May 21,1985 in the residual heat removal (RHR)
Joseph, Michigan 49085. discharge line to the liquid radwaste (50 FR 20969 at 20983). The Iouisiana Power and Ught Co., Docket Commission's related evaluation of the system.
I No. 50-382. Waterford Steam Electric amendment is contained in a Safety Date ofissuance: March 31,1987 Station, Unit 3, St. Charles Parish, LA. Evaluation dated March 26,1987.
Effective date: March 31.1987.
Dates of applications for amendment: co en ceiv N. AmendmentNa 29.
\ October 15.1986, as supplemented bY LocalPublic Document Room Facility Opemting License Na NPF-letters dated November 19,1986 and location: Wiscasset Public Library, High a This amendment revised the February 9,1987. Street, Wiscasset, Maine. Technical Specifications.
Briefdescription of amendment:The Date ofinitialnoticein Federal admendment revised the Technical Maine Yankee Atomic Power Co.,
Register. February 26,1986 (52 FR 5862),
a zational c a e i Sec lons 6 to An ow ti n I colo unty, He Commission's related evaluation reflect the reorganization within IP&L s ME of the amendment is contained in a Safety Evaluation dated March 31,1987, Nuclear Operations group.The Date of applicaticafor amendment:
November 19,1986 and February 9,1987 April 3,1981 as supplemented April 10. No significant hazards consideration letters were explanatory in nature and 1984 and September 12,1985. c mments received: No LocalPublic Document Room
{
did not make any substantive changes. Briefdescription of amendment:%e l Date ofissuance: April 3,1987, amendment revised the testing location: Hinds Junior College, l Effective date: April 3,1987, requirements for hydraulic shock McLendon Library, Raymond, i Amendment No. 18. suppressors (snubbers) and added Mississippi 39154 l l
l
NS58 Federal ReS i ster / Vcl. 57. No. 77 / Wedn sdry, April 22,1e87 / Noticss Mississippi Power & usht Co., System Effect/w date: March 31,1987. Date ofinitiolnotice in Federal Amendment No. 31. Register: September 10,1986 (51 FR Energy Resources,Inc., South .
! Missimippi Electric Power Assodation, Facility Opemting LicenseNo. NPF- 322e4 at 32278).
I Docket No.EMis Grand Gulf Nuclear M.This amendment revised the ne Commission's related evaluation Station, Unit 1, r'Ind==ne County, MI Technical Specifications. of the amendment is contained in a l Safety Evaluation dated March 26.1987. -
Date of applicationforamendment:
Date ofinitiolnoticein Federal No significant hasards consideration i May 22.1986 as revised December 9 Re.g.h Comminion's related evaluationgister:
comments received: February No. 26,1987 (52 FR 586 j 1986 and January 29.1987. of the amendment is contained in a LocolptiblicDocument Room Briefdescnption of amendment:His Safety Evaluation dated March 31,1987. location:W. Dale Clark Ubrary,215 amendment changes the Technical No significant hazards consideration South 15th Street, Omaha, Nebraska
- Specifications (TSs) for attemating comments received
- No. 08102.
, current electrical power nystems by . Loco /Public Document Room
- reducing excessive test.r.g of the three location: Hinds Junior College, Omaha Pubhc Power District. Docket No. 56 385. Fort r' atha == Station, Unit i onsite emergency diesel generators to be McIAndon Ubrary, Raymond.
consistent with th recommendations No. I, Washington County, NE. <
Mississippi 39154.
4 provided in the NRC Generic latter 84- Date of application for amendma.u-5 15 " Proposed Staff Actions to Improve Mississippi Power & Ught Co., System January 7,1906 [sicl-(1987).
and Maintain Diesel Generator Energy Resourose Inc., South Capdon ofomendmenGe .
Reliability." Mississippi Electric Power Association, Docket No.58 414, Grand Gulf Nmelser at modifies the surveillance l Date afissuance: March 31,1987. requirements for the hydrogen and Effective date: March 31,1987. Station, Unit 1 Claiboras County, MS oxygen monitonna system for the waste
, Amendment No. 30. Date ofapplicationforamendment' gas decay tanke to clarify that a daily
/ity n Li e o. NPF- November 11.1988, as revised January channel check is required for this
! T Briefdescription of amendment:%e Do of March 1987.
Register: February 26,1987 (52 FR 8859). T ica fica ted g ,,
i a v a 11 .
t ti im Specifications.
j
- No sigmficant hazards consideration by the vendor for the nuclear steam , ,
Date ofinitiolnotice m Federal i
comments received: No LocalPublicDocumentRoom I,'['"' '"' I' I' Register: February 11,1987 (52 FR 4400 i
Mclan Mississippi 39154.
brary hr '
doteha Amendment No. 32.
8 "
of ee amendinentis contained in a Se ty
- I'"
on
I*d *I'*II'"
1 l Mississippi Power & Ught Co., System facility Opemt/rg License No.NPF- ,
Energy Resources,Inc., South W.This amendment revised the g g^
Mississippi Electric Pewar Asmodation. Technical Specifications.
- Loco /Ptiblic DocumentRnom Docket No.88-418, Grand Gulf Nedeier Date ofinitiolnotimin Federal I* W U U
)
- 1 Station, Unit 1, Claiborne County, MS Date of applicationforomendment:
p ] ry 1 52 8083 g,,
- 102-g ,
- of the amendment is contained in a May 28,1988 as amended November it. Safety Evaluation dated March 31.1987 Omaha Public Power District. Docket 1986 and Februe,ry 13.1987. No significant hazards consideration No.as. ass, Fort r' atha-t Station Unit l
Brie comments rsceived: No. No.1,Waeldnetes County, NE
- j. amen [ent description changes theTechnical ofamendment This loco /Public Document Room Specifications (TSs) for the drywell location: Hinds jsnior College, Date of applicationforamendment airlock by: (1) Changing the wording to January 8,1988 [ sic] (1987).
Mclandon ubrary, Raymond.
i indicate only one drywell airlock:(2) Mississippi 39154.
Enefdescriptionofamendmentne amendment deleted the hydrogen rearraging Action Statement "a" to clarify that all actions in the statement Omaha Public Power District Docket flouride detectors from Tables 2-11 and No. so-ass, Fort r'alha-t Station, Unit 3 -8 of the Technical Specifications.
are parts of the same action:(3) changing the drywell overall airlock No.1,Washlagtee County, NE Dofe ofisevonce: March 30,1987 leakage test frequency from the present, Date ofappliostionforomendment: Effective date March 30,1987.
once per six months, to each cold August 19,1986. AmendmentNo.:107. ,
shutdown if not performed within the Briefdescription of amendment:%e Focility Operating License No. DPR-previous six months; (4) changing the amendment deleted the tabular listiass 50. Amendment revised the Technical eurveillance requirement regardmg the of safety-related snubbers from the Specifications.
J verification that only one door in the Technical Specificatione in accordance Date ofinitiolnotscein Federal .
airlock can be opened at a time from with GenericIstter 86-13 Register. February as,19e7 (52 FR 5e84).
once per six months to once per 18 Date ofissuance: March 28,1987. The Commission's related evaluation i,
months: and (5) changing the drywell Efffective date:Within 30 days of of the amendment is contained in a airlock infletable seal pressure issuance. Safety Evaluation deted March 30,1987, 3
instrumentation channel functional test Amendment No.:106. No significant hazards consideration 1
from once per 31 days to once per18 Focility Operating License No. DPR- comments received: No.
months. e. Amendment revised theTechnical Loco /PublicDocument Room Date ofissuance: March 31,1987. Specifications. location: W. Dale Clark Ubrary,215 i
'Ie[- ..,__-_..e - - - . - - . -,-r- .--r,---,--e--.-.-r- -,-r ,-_,r.w - . - . ,,-,---,-m y -v,,,---- -,c--,--.m,m_,---,,.-,.--r- . - . , , , , . -
Federal Register / Vol. 52. No. 77 / Wednesday, April 22, 1987 / N:tices 13359 South 15th Street.Omsha. Nebraska appropriate information in accordance Portland General Electric Co., et al.,
08102. with Generic Latter 85-19. Docket No.34444. Trojan Nuclear Pennsylvania Power ai Usht Co Docket (5) Snubbers Unit 2:Two changes Plant. Columbia County,OR Nos.30-387 and 36 38s, Susquehanna have been made to specification 3/4.7.4:
Date of applicationfar amendment:
Steam Electric Station. Units 1 and 2' Luzerne Coanty, PA fR v u
- October 31,1986.
approved by NRC via Amendment 36 to briefdesenption of amendmentThe Date ofapplicationforamendments the Unit 1 Operating Ucense.The amendment revises the reactor veasal December 25,1985. references to it were inadvertently left usaterialirradiation surveillance Brief description of amendments: The in the text of Specification 3/4.7.4. (2) schedule and the pressure-temperature licensee in their December 26,1985, Correction of sampling expression. De limits.
submittal requested several Technical correct expression is 35 (1 + C/2). Date ofissuance April 9,1967.
Specification changes for Units 1 andfor Date ofissva.nce: April 6,1987. Effectivedate April 9.1987.
2 which are administrative in nature. Effective date: April 6,1987.
n pecification changes are Amendment No. 127 AmendmentNos. 63 and 34 Facnities Opemting .icenseNo.NPF-(1) Corrections' to Table 3A3-1 (Units y[#hy "[#8,Y,8"8 [F~ 1: Amendment revised the Technical Specifications.
1 and Unit 2) (a)3/4 1:Page Containment Instrument 6-25 of the Unit 1 Gas the Technical SEecifications ,
Dates ofinitialnoticein Federal Date ofinitialnoticein Federal .
Techrucal Specifications (TS) previously Registen February 26,1987 (52 FR 5865).
Registen May 21,1986 (51 FR 18690).
listed valve number 1-26-070 as an ne CommWlon's related evaluation The t'ammission's related evaluation foolation valve m the Catainment of the amendment is contained in a of the amanAmants is contained in a Instmnen,t Gas System.ne amendment Sa Uhtion dated April 6,1987. Safety Evaluation dated April 9,1987. ]
alve n er 26- 6 i No significant hazards consideration No *iWant hazards consideration i Page 3/4 6-25 of the Unit 2 Technical comments received: No. comments received: No. .
Specifications deletes valves 2AS-070 Loca1PublicDocument Room Loca1Public Document Room 1 from Table 3A3-L (b) High Pressure location:Osterhout Free ubrary. Jocation Multnomah County Ubrary, 4 Coolant Injection (HPCI) Unit 1:The Reference Department 71 South 801 S.W.1oth Avenue,, Portland, Oregon i amendment adds valve HV-155F046 as Franklin Street, Wilkes. Barre, 97205, Pennsylvania 18701. l a Minimum Recirculation Flow
[ penetration X-211) isolation ..tve on Po ad General Electric Capany,et York. Docket No.56-333, James A.
Page 3/4 6-26. Unit 2: Page 3/4 6-25: the al, No.58-444.Trojaa Nuclear FitzPatrick Nuclear Power Plant, amendment adds valve HV-255F046 as Plant. Columbia County, OR a Minimum Recirculation Flow isolation Os**8' CounIY' NY )
valve. (c) Reactor Core Isolation Cooling Date of applicationforamendment Date of application for amendment:
(RC!C) Unit 1:Page 3/4 6-26 lists HV- Janary 31.1986, as supplemented May December 19,1986, as supplemented 149F019;the amendment adds HV- 16,1980 and February 26,1987.
January 3,1987 and March 13,1987.
Brief descriptron of amendment The 149F021 as a RCIC minimum ,
recirculation flow (penetration X-216) amWe revises the Technical WWon ofedende J Specification (IS) by providing editorial amendment changes Table 3.7-1 of the j isolation valve on Page 3/4 6-26. Unit 2- Technical Specifications to reflect '
Page 3/4 6-28: the amandmant adds corrections to TS Sections 4.441.b and 3.4.9.3. Table 3.6-1 is revised to permit installation of new containment valve HV-249Ft)21 as a mmimum the operation of valve MIM69 to be isolation valves in the Traveling Incore Recirculation Flow isolation valve. (d) Probe Purge System. Recirculation Pump lotegrated Leak Rate Testing (IIRT) Unit administratively controlled in order to f: Page 3/4 6-24 contained a provide consistency between TS Mini-Purge System, and ADS .
typographical error. Valve 1-57-195 now Sections 3.6.1.1,3.6.3.1 and 3.7A3. Accumulator System.
reads 1-57-194. By letter dated February 26,1987. PGE Date ofissuance: April 3,1987.
(2) Addition to Plant Operations requested that the portion of this. Effective date: April 3,1987.
Review Committee (PORC) Membership application pertaining to the deletion of Amendment No.:108.
Units 1 and2:The licensee has added valve CV-8825 from Table 3.6-1 be FacHity Opemting License No. DPR-the Assistant Superintendent-Outages to withdrawn. 59. Amendment revised the Technical the PORC Composition listing in Section Dateofissuance April 2,1987. Specifications.
6.51 * *
- 3) eletion of Offsite Organization Am t o Date ofinitialnoticein Fedeal
- **'**** I""* 'I ** ' # (** *** I' Position Units 1 and2:The deletion oi Facilities Openting License No. NPF- The January 3 and M' arch 13,1987 the position "Vice President-Engineering 1: Amend nent revised the Technical and Construction-Nuclear" and the Specifications. submittais provided clarifying subsequent realignment as indicated in inf rmation and did not change the Date ofinitist notice in Federal finding of the initial notice.
Figure 6.2.1-1 reflects PP&L's shift from Registen Pih 30,1986 (51 FR 27287).
constniction to operation of the The Commission's related evahzation The Commission's related evaluation l Susgehanna plant. of the amendment is contained in a of the amendment is contained in a l (4) Ceneric Lett2r No.85-19 Units 1 Safety Evaluation dated April 2,1987. Safety Evaluation dated April 3.1987, and2:%e licensee has changed both Na significant hazards consideration No significant hazards consideration l Units 1 and 2 Technical Specifications corements received: No. comments received: No.
based on the recommersiatious of LocarlPublic Document Room LocalPublic Document Room Generic Letter 65-19. " Reporting location: Multnomah County Library, location: Penfield Library. State Requirements on Primary Coolant lodine 801 S.W.10th Avenue. Portland, Oregon University College of Oswego. Oswego, Spikes".The licensee has added the 97205. New York.
13360 Federal Register / Vol. 52, No. 77 / Wedn:sdiy. April 22, 1987 / Noticcs Power Authority of the State of New Power Authority of The State of New Brief description of amendment: This York Docket No. 50-333, James A York, Docket No. 50-286, Indian Point amendment revises the Technical FitzPatrick Nuclear Power Plant. Unit No. 3 Westchester County, NY Specifications to permit long-term Oswego Couq, W Date of application foramendment: Operation with one recirculation loop Date of applicationforamendment: . January 14,1987. out of service.
December 23,1988, as supplemented Briefdescription of amendment:The Date ofissuance: April 7.1%7.
March 13,1987. amendment revises the Technical Effective date: April 7.1987. l Briefdescription of amendment:%e Specsfications to permit the discharge of :
more than one region of fuel (72 Amendment No.:3. I cmendment changes the Technical Specifications to permit fuel reloading assemblie4) from the reactor after 162 Facility Opemting License No. NPF-cnd Cycle 8 operation. included in the hours have elapsed since shutdown. 57: Amendment revises the Technical Cycle 8 core will be four Westinghouse This elapse time was 400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />. Specifications.
QUAD + demonstration fuel assemblies. Date o[ issuance: April 2,1987.
Effecove date: April 2,1987. Date ofinitialnon,ce m, the Federal Date ofissuance: April 3,1987' Register: January 28,1987 (52 FR 2889).
. Amendment No. 72. .
Effech.ve date: April 3,1987. Facilities Operating License No. %e February 7,1987, submittal AmendmenMa 109. DPR-N: Amendment revised the provided clarifying information and did Facility Operating License No. DPR- Technical Specifications. not change the finding of the initial *
- 59. Amendment revised the Technical Date ofinitialnotice in Federal notice
- Specifications. Register: February 28,1987 [52 FR 5866).
Date ofinitialnoticein Federal The Commission's related evaluation The Commission's related evaluation Register: January 28,1987 (52 FR 2888). of the amendment is contained in a of the amendment is contained in a ne March 13,1987 submittal Safety Evaluation dated April 2,1987. Safety Evaluation dated April 7,1987.
provided clarifying information and did No significant hazards consideration No significant hazards mnsideration n:t change the finding of the initial comments received: No.' comments received: No.
n:tice. LocalPublic Document Room LocalPublic Document Room he Commission's related evaluation location: White Plains Public Ubrary.
lomuon:Pennsville Public Ubrary,190 cf the amendment is contained in a 100 Martine Avenue, White Plains, New Safety Evaluation dated Apnl 3.1987. South Broadway, Pennsville, New Jersey York.10610.
No significant hazards consideration Public Service Company of Colorado, Docket No. 50-267. Fort St. Vrain Sacramento Municipal Utility District, Local Ic ment Room Nuclear Generating Station, Platteville, Docket No. 50-312, Rasicho Seco location:Penfield ubrary State .CO Nuclear Geaerating Station, Sacramento University College of Oswego, Oswego.
Dcte of application for amendment: County, CA New York.
Power Authority of the State of New ecem 27,1984 Dcte of applicationfor amendment:
York, Docket No. 5M33, James A. December 18,1984, as revised April 26, Briefdescription of amendment:%e FitzPatrick Nuclear Power Plant, amendment increases the Circulator 1985, supplemented May 22,1985, and Oswego County, NY Speed-High Steam trip setting listed in superseded October 30,1985.
Date of applicaticaforamendment: Table 4.4-3 of the Technical '
Brief description of amendment: This September 19,1985. SPecifications, amendment revised the TSs by Briefdescription of amendment:The Date ofissuance: April 6,1987. establishing limiting conditions for amendment changes the Technical Effecuve date April 6,1987. operation based on the Spent Fuel Pool Specifications to revise notification and Amendment No.:52. . (SFP) water temperature. It included reporting requirements, as reqaested by Facility Operating License No. DPR-requirements for use of the Decay Heat
- 34. dment revised the Technical NRC Generic letter 83-43 dated December 19,1983, to be consistent with p Red SW n a hW supplemental SFP cooling means when the new requirements in 10 CFR FO.72 te ofin alnoucein Federal SFP temperatures reach specified limits.
Register: June 20,1984 (49 FR 25372).
The December 27,1984 submittal Date ofissuance: March 31.1987.
ate o issuanm April 3,1987. provided supplemental information and Effective cate: March 31,1987.
Effech.vc dote: April 3,1987. did not change the initial determination Amendment No.:84.
Fac 1 t l] cense No. DPR- (amendment 'fg. ;, ,,gfo*a'nfty, I FamMy Opmung L.icme Na MR-n Amendment rewed 6eMnkal
- 59. Amendment revised the Technical is contained in a Safety Specifications. Spedcanono Evaluation dated April 6,1987. ,
Date afinitialnoticein Federal No significant hazards consideration Date ofinitialnoticein Federal Register: November 20,1985 (50 FR comments received: No. Register: June 4,1986 (51 FR 20373).
47869). LocalPublic Document Room The Commission's related evaluation The Commission's related evaluation location: Greeley Public Library, City of the amendment is contained in a of the amendment is contained in a Complex Building, Greeley, Colorado. Safety Evaluation dated March 31,1987.
Safety Evaluation dated April 3.1987. Public Service Electric & Gas Co., No significant hazards consideration No significant hazards consideration Docket No. 50-354 Hope Creek comments received: No.
comments received: No. Generating Station, Salem County, NJ LocalPublic Document Room LocalPublic Document Room location: Penfield Library, State \ Dates of application for amendment: location: Sacramento City-County University College of Oswego, Oswego. May :>0.1988, as supplemented on Library,828 I Street Sacramento, l New York. December 24,1988, and February 6,1987 California 95814.
l i
Fed:r:1 Rrgister / Vol. 52 No. 6'/Madnesday, Ahrd 22.'1987 / Nstices 13381
. South Carolina Electric & Gas Co., South South Carolina Electric & Gas Co., South LocalPublic Document Room Carolina Public Sonia Authority, Camlina Public Service Authority, location: Fairfield County Library, Decket No.56-395, Virgil C. Summer Docket No. 55-395, Virgil C. mi= mar Garden and Washington Streets, )
Nudeer Station, Unit No.L Fairfield Nuclear Station. Unit No.1, Fair 6 eld Winneboro South Caroline 20180.
County, SC County, SC Sostem Cellforude Beson Ca, et d.,
Date of applicationforonwndment: Date ofapplicationforamannenent: DesetNes,nsagt adgo.agg,saa June 27.1988, as supplemented December 9,1986, as -;;' - 'S Onofre Nucles Generadag Station.
November 21,19a6, and February 25. March 2.1987. Units 2 and 3,1am Diego County, CA 198 '
amen the hier ofa#.mtienefor Briefdescription of amendmerrt %e flexibility to recoestitute fuel amendmerrie:Merd 17. June 13.and amendment reduces the reactor coolant asserablies. September 30,19e(Reference PCN-system flow measurement uncertainty Data issusce.- 192).
2.1987.
Emm 3.5% to 2.1%. Effective date: Ap@riJ 2,1987. Briefdescrption ofcars&nerrts:%e Date ofissuance: March 30,1957. Amandmaar No.: a2.
amendments revise Todmical '
Effective date: March 30,1987. Facility Opamting Licenne No.NPF- Specification 3/4.8.1.L "Esctrical Power Amendment Na 60. 22. Amendment revised the Technical Systems. AC Sources." asanarning facility Opemting Licenne No.NPF- Specifications, reduced frequency of Emergency Diesel
- 12. Amendment revised the Technical Date ofirritiolnoticein Fedesel Generator [EDG) fast starts. reduced Specifications. Register: February 28,1987 (52 FR 5888). number of EDG tests and revised diesel The March 2.1987 letter provided fuel oil survaallanar Date ofinitialnoticein Federd suPpWatal h M M nd &te ofiesames- Apre e,1ser.
Registen July 30,1986 (51 FR 27289).
The letters dated November 21.1986, 8n88 8 8 8 8 n Mec#m deter AprH e,1987 to be -
pub i had .
Insplemented ofisenance.
and February 27,1988, pmvided supplemental information and did not of the amendment is contained in a
. change the initial determination Safety Evaluation datad April 2.1987
"# I " #'* ~
published in the FederalRegister. No signi&mnt hazards ennaidaration 20andm'A Amndent Wee &e r
The 'amminaion's related evalma'$an Technial Specifications.
comments received:No.
of the amendme le mn*= sand to a LocalPublicDocumentRoom Date ofinitialnoticesin Federal Safety Evaluation dated March 30,1987. locarba:Faidield County Library, Register: February '11,1987 (52 FR 4418).
No signifh ant hazards cceeideration Garden and Washington Streets, %e Comminalon s related evaluation consnents received: No. Winnsboro, South Carolina 29180. of the amendment is containedin a Loca/PublicDocumentRoorrr 8' #v E aUon Apru 9,1 7 Beuth Coralks Bede a Gas Ca South gI" __
locatiorrFairfield County Ubrary, f'a== ham Puhuc Servios Ausherity Garden and Weehington Streets. emnants aceivh Docket No. 56-ass, Virgil C. Summer """
Winnsboro, South Caroline 29180. I#"I Nuclearmaan== Unit No. L Fairfisid location: General Ubrary, University of South Carolina Electric & Gas Co, South County, SC Caldarnia at Irvine, Irvine. California Carolina Public Service Anthority, Date ofapplicationforomendment: 92713.
nach at Na 50-3a5. Virgil C. Li==ar April 29,1965 as supplemented June 10 Nuclear Anatian Unit Na1.Fairfield 1985.
Union Electric Co., Docket No.88-483, County, SC Briefdescription of amendmentThe Canemy Fleet. Unit L Canaway amendment revises Technical County, MO ,
D 1 SPecification (TS) 3/4.a.4 " Electrical Date of[qpplicationforamendment l Equipment Protective Devices" by January 9,190&
Bri descriptw.n of amendment %e indicating which devices are required to
+
amen ent increases the required Brisfdescenption of amendment:he '
be operable and by eliminating the amendment modifies the Technical boron concentratien for the specific list of electrical equipment Specifications to regnire 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> accumulators and the refueling water protective devices for contatmn""'
storage tank- restoration in the event of lose af one of penetrations (Table 3.8.1) from the TS. the diverse reactoe trip features, Date ofissuance: March 3L 1987. The amendment also incorporates the inds. pendent verification of the Effective date: March 31.1987. ariministrative page rmmharing changes operabuity of the undervoltage and A mendmant No. 61. to the Index and the TS pages that are shunt trip attachments, and independent
- Facility OpemtagI/censeNo. NPF- necessary as a result of deleting the testingof thecontrolroommanual
- 12. Amendment revised the Teantral table. reactor trip switch contacts during each
. Specif cations. Date oflasuance ril 6.1987. refuehng ostage.
&te ofinitialnotamin Federal D feof188uonC8: April 3,1987.
Register: February 28,1987 (52 FR 5856).
8[d ent 63 Effective date Apr0 3,1987.
7,,fjjf7 gp,,,ff,, jfy,,,, g,, gpg_
. He Commission's related evaluation 12. Amendment revised the Technical Amendnent No.119.
of the amendment is contained in a Specifications. Facility OpemtingLicense No. NPF-Safety Evaluation dated March 31,1957. Date ofinitialnoticein Federal 3dt Amendment rettsea the Technical No significant hazards consideration Registec April 9.1986 (51 FR 12239). Specifications.
comments recerved: No. The Commission's related evaluation Date ofinitialnotice in Federal localPublic Docenent Room cf the amendment is containedin a Registen August 27,1986 (51 FR 30583).
l location Fairfield County Library, Safety Evaluation dated April 6,1987. The Commission's related evaluation Garden and Washington Streets, No significant hazards consideration of the amendment is contained in a Winnsboro, South Carolina 29180. comments received: No. Safety Evaluation dated April 3,1987 l
,13362 Feder-1 Register / Vol. 52.Wo. 77 / W:.dmsdry, Ap'ril 52, 1987 / Notices No significant hazards consideration Facility Opemting License Nos.NPF- Date ofinitialnotice in Federal comments received: No. 4 andNPF-7. Amendments revised the Register: August 13,1988 (51 FR 20016).
LocalPublic Document Room Technical Specifications. The Commission's related evaluation location Fulton City Ubrary,709 Market Date ofinitialnoticein Federal of the amendment is contained in a Street, Fulton, Missouri 85251 and the Register: February 28,1987 (52 FR 5870). Safety Evaluation dated March 31,1987, Olin Library of Washington University. The Commission's related evaluation ' No significant hazards consideration Skinker and undell Boulevards, St. of the amendments is contained in a comment received: No.
leuis, Missouri 83130. Safety Evaluation dated March 31,1987. Local Public Document Room location:
No significant hazards consideration Richland Public Ubrary, Swift and Vermont Yankee Nuclear Power Corp., comments received: No. Northgate Streets, Richland.
Docket No. 50-271 Vermont Yankee LocalPublicDocument Room Nuclear Power Station, Vernon, VT Washington 99352.
locations: Board of Supervisors Office, i Date of applicationforamendment: Iouisa County Courthouse. Imulsa, Notice ofIssuance of Amendment to (
linuary 30,1979, as supplemented Virginia 23093, and the Alderman Facility Operating Ucense and Final i November 27,1964. Library, Manuscripts Department, Determination of No Significant Hazards Briefdescription of amendment:ne University of Virginia, Charlottesville. Consideration and Opportunity fw .
cmendment changes the Technical Virginia 22901. Hearing (Exigent or Emergency Specifications to require that the Circumstarw=a)
Washington Public Power Supply inservice examinations of the piping. During the period since publication of .
components, and their supports be S,ystem. Docket No. 50,397, WNP-2 the last bl. weekly notice, the performed in accordance with 10 CFR - di=~l WA
~
Commission has issued the following 50.55a[b)(2) rather than by an earlier Date of amendmentrequest: July to, amendments.ne Commission has edition of the ASME Code Section XI. 1986. . determined for each of these !
The remainder of the requests contained Briefdescription of amendment:This amendments that the application for the I in the January 30,1979 and November amendment revises WNP-2 Technical amendment complies with the standards 27.1964 applications pertain to NRC's Specification 3.4.2 (Safety / Relief and requirements of the Atomic Energy continuing review of the inservice Valves) and Bases Section 3/4.4.2 to Act of 1954, as amended (the Act), and Inspection and Inservice Testing reflect revised safety / relief valve the Commission's rules and regulations.
programs, and will be acted upon setpoint tolerances for all18 valves and The Commission has made appropriate separately, to reflect a, revised setpoint for 2 valves. findings as required by the Act and the Date ofissuance: March 31,1987. Date ofwssuance: March 27,1987. Commission's rules add regulations in 10 Effective date: March 31,1987. Effective date: March 27,1987. CFR Chapter I, which are set forth in the Amendment No.:99. Amendment No.:38. .
yC'*** ****g,"
Facility Operating License No.DPR- Facility Opemting License No. NPF-endment revised the Technical oment revises the Technicsi ,"tances ated $th date the amendment was needed, there was Date ofinitialnotice in Federal Date ofinitialnoticein Federal ,
not time,fw the Commission to publish, Register: August 23,1983 (48 FR 38425). Registen September 10,1988 (51 FR The November 27,1984 submittal for p ibhc comment before issuance, its 32282). usual 30-day Notice of Consideration of provided additional clarifying he Commission's related evaluation Issuance of Amendment and Proposed information and therefore did not of the amendment is contained in a change the determination of the initial Safety Evaluation dated March 27,1987. No Significant Hazards Consideration Federal Register notice. No significant hazards consideration Determination and Opportunity for comments received: No. Hearing. For exigent circumstances, the The Commission's related evaluation of the amendment is contained in a LocalPublic Document Room Commission has either issued a Federal Safety Evaluation dated March 31,1987. location: Richland Public Library, Swf ft Register notice providing opportunity for No significant hazards consideration and Northgate Streets, Richland. public comment or has used local media comments received: No. Washington 99352. to provide notice to the public in the LocalPublicDocumentRoom area surrounding a licensee's facility of Washington PubEc Powee Supply the licensee's application and of the 1^ cation: Brooks Memorial Library,224 Main Street, Brattleboro, Vermont 05301. System, Docket No. 50-397 WNP-2, Commission's proposed determination Richland, WA of no significant hazards consideration.
Virginia Electric and Power Co., et al., Date of amendment request:May 27 The Commission has provided a
' Docket Nos. 50-338 and 50-339, North reasonable opportunity for the public to 1988.
Anna Power Station Units No.1 and No Briefdescription of amendment his comment using its best efforts to make
- 2. Imuisa County, VA amendment changes the reporting available to the public means of Date of application for amendments: requirements for iodine spiking to communication for the public to respond
- November 25,1988. eliminate the short term reporting quickly, and in the case of telephone Brief description of amendments: The requirements of Technical Specification comments, the comments have been cmendments modify Technical 3.4.5,instead requiring that iodine spike recorded or transcribed as appropriate Specifications 3/4.12 (Radiological reporting be added to the Annual Report and the licensee has been informed of .
Monitoring) to reflect established required by Technical Specificatton the public comments.
practices, to agree with NRC approved 8.9.1.5. In circumstances where failure to act documents, and to conform to NRC Date ofIssuance: March 31.1987. in a timely way would have resulted, for guidance. Effective Date: March 31,1987, example,in derating or shutdown of a Date ofissuance: March 31,1987. Amendment No.139. nuclear power plant or in prevention of Effective date:14 days from the date Facility Opemting License No. NPF- either resumption of operation or of cf issuance. M Amendment revises the Technical increase in power output up to the AmendmentNos. 92 and 77. Specifications. plant's licensed power level, the
Fed:r:1 R: gist:r / Vol. 52. No. 77 / Wednesday April 22, 1987 / Notices 13363 l l
Commissior. may not have had an interest may be affected by this limitations in the order granting leave to opportunit) to provide for public proceeding and who wishes to intervene, and have the opportunity to comment on its no significant hazards participate as a party in the proceeding participate fully in the conduct of the determination. In such case. the license must file a written petition for leave to hearing, including the opportunity to amendment has been issued without intervene. Requests for a hearing and present evidence and cross examine opportunity for comment. lf there has petitions for leave to intervene shall be witnesses. Since the Commission has been some time for public comment but filed in accordance with the made a final determination that the less than 30 days, the Commission may Commission's " Rules of Practice for amendment involves no significant provide an opportunity for public Domestic Ucensing Proceedings" b io hazards consideration,if a hearing is comment. If comments have been CFR Part 2. If a request for a hearing or requested. It will not stay the requested. it is so stated. In either event, petition for leave to intervene is filed by effectiveness of the amendment Any tne State has been consulted by the above date, the Commission or an hearing held would take place while the telephone whenever possible. Atomic Safety and Ucensing Board, amendment is in effect.
Under its regulations. the Commission designated by the Commission or by the A request for a hearing or a petition may issue and make an amendment Chairman of the Atomic Safety and for leave to intervene must be filed with
- immediately effective, notwithstanding Ucensing Board Panel, will rule on the the Secretary of the Commission. U.S.
the pendency before it of a request for a request and/or petition and the Nuclear Regulatory Commission.
hearing from any person. in advance of Secretary or the designated Atomic Washington,DC 20555 Attention:
the holding and completion of any Safety and Licensing Board will issue a Docketing and Service Branch, or may required hearing, where it has notice of hearing or an appropriate be delivered to the Commission's Public determined that no significant hazards order. Document Room.1717 H Street NW.,
consideration is involved. As required by 10 CFR 2.714. a Washington, DC. by the above date.
The Commission has applied the petition for leave to intervene shall set Where petitions are filed during the last standards of to CFR 50.92 and has made forth with particularity the interest of ten (10) days of the notice period,it is a final determination that the the petitioner in the proceeding and how requested that the petitioner promptly so amendment involves no significant that interest may be affected by the inform the Commission by a toll. free hazards consideration. The basis for this results of the proceeding.The petition telephone call to Western Union at (800) determination is contained in the shoul,d specifically explain the reasons 325-6000 (in Missouri (600) 342-6700).
documents related to this action. why intervention should be permitted ne Western Union operator should be .
Accordingly, the amendments have been with particular reference to the given Datagram Identification Number issued and made effective as indicated. following factors:(1) The nature of the 3737 and the follo3ving message Unless otherwise indicated, the petitlener's right under the Act to be addressed to(ProjectDirector)'-
Commission has determined that these made a party to the proceeding: (2) the Petitioner's name and telephone amendments satisfy the criteria for nature and extent of the petitioner's number; date petition was mailed; plant categorical exclusion in accordance property, financial, or other interest in name: and publication date and page with 10 CFR 51.22. Therefore, pursuant the proceeding: and (3) the possible number of this Federal Register notice.
to 10 CFR 51.22(b). no environmental effect of any order which may be A copy of the petition should also be impact statement or environmantal entered in the proceeding on the sent to the Office of the General assessment need be prepared for these petitioner s interest. The petition should amendments. If the Commission has Counsel-Bethesda. U.S. Nuclear also identify the specific aspect (s) of the Regulatory Commission. Washington, prepared an environmental assessment subject matter of the proceeding as to DC 20555, and to the attorney for the under the special circumstancas which petitioner wishes to intervene.
licensee.
provision in 10 CFR 51.12(b) and has Any person who has filed a petition for made a determination based on that leave to intervene or who has been Nontimely filings of petitions for leave assessment, it is so indicated. admitted as a party may amend the to intervene, amended petitions.
For further details with respect to the petition without requesting leave of the supplemental petitions and/or requests action see (1) the application for Board up to fifteen (15) days prior to the for hearing will not be entertained first prehearing conference scheduled in absent a determination by the amendment. (2) the amendment to Facility Operating License, and (3) the the proceeding, but such an amended Commission, the presiding officer or the Commission's related letter. Safety petition must satisfy the specificity Atomic Safety and Licensing Board, that requirements described above. the petition and/or request should be Evaluation and/or Environmental Assessment, as indicated. All of these Not later than fifteen (15) days prior 8 ranted based upon a balancing of the items are available for public inspection to the first prehearing conference factors specified in 10 CFR 2.714(a)(1)(i) at the Commission's Public Document scheduled in the Proceeding, a petitioner through (v) and 2.714(d).
Room.1717 H Street, NW., Washington. shall file a supplement to the petition to Alabama Power Co Docket Nos.56-348 DC, and at the local public document intervene which must include a list of and 56-364. Joseph M.Farley Nuclear room for the particular facility involved. the contentions which are sought to be Plant. Unit Nos.1 and 2. Houston A copy ofitems (2) and (3) may be litigated in the matter, and the bases for County, AI obtained upon request addressed to the each contention set forth with U.S. Nuclear Regulatory Commission. reasonable specificity. Contentions shal] Dote ofopplicationfor omendments:
- Washington, DC 20555. Attention: be limited to matters within the scope of September 2.1986, as supplemented Dir : tor. Division of Licensing. the amendment under consideration. A February 9,25. and 27.1987.
Lie Commission is also offering an petitioner who fails to file such a Briefdescription ofomendments:
opportunity for a hearing with respect to supplement which satisfies these Technical Specification (TS) 4.7-4 is the issuance of the amendments. By June requirements with respect to at least one changed on a one-time basis and Table 5.1987, the licensee may file a request contention will not be permitted to 4.7-3 is added for the same time periods.
for a hearing with respect to issuance of participate as a party. De changes are reisted to visual the amendment to the subject facility Those pennitted to intervene become inspection requirements of snubbers at operating license and any person whose parties to the proceeding subject to any both units and are based on the 1
13364 ' Federal Register / Vcl. S2. Ns. 77 / Wedneed y April 22, 1987 / Nitices tpplication of statistical methodology consideretion Yes (52 FR 7348. March Briefdescription of amendment his while meeting the ex.isting confidence 10.1987). By letter dated March 19.1987, amendment revised the ' Ilia to change levels. & February 25.1987, nosest is the licensees submitted information from four to three the minimum nurnber a revision of the September 2.1988, concerning future activities relative to of sequencer channels for emergency request. the RCIC System but this information diesel generator loeding required to be Date ofissuance: March 30.1987. did not change the initial application or operable.
Effective date: March 30.1987. result in changmg the no significant Date oflasuance April 3. 2887.
Amendment Nos 60 and 61. hazards determination. %erefore, no EffectiveDate April 30.1987.
Facilities Opemting UcenseNos. renotice of the application was
- "*" "'#t #": 102.
NPF-2andNPF-8. Amendments revised warranted.
the Technical Specifications. He t'ar== nasion's related evalaation Facility Opestig 6 Na NPF4 Public comments requested as to of the amendment, consultati-a with the Amendment revised the Tednical proposed no significant hazards State of Ohio, and finally no significant Specifications.
consideration: No. Comments were hazards comederations determination Public comments requested as to requested on the initial application of are contained in a Safety Evaluation proposed no significant hasards September 2.19ee, which was noticed dated April 1.19s7. consideration: No.
on Octobe; 22.1986 (51 FR 37503).No AtrorneyForhaemoset }ay Silberg. State Contacted:In accordance wah l significant hazards consideration Esq., Shaw. Pittman Potts a the Commission's regulations, comments received: No.The Trowbridge,2300 N Street. NW, consultation was held with the St ste of
- Commission's related e,sluation of the Washington. DC 20037. Ohio by telephone.h state expressed amendment, and final no significant LocolPublicDocumentRoom no concem either from the standpoint of hazards considerations determination location: Perry Public Ubrary 3753 Main refety or of our no significant hazards tre contained in a Safety Evaluation Street. Perry. Ohio 44081. consideretion determination.
dated March 30.1987. NRCProject Director: Walter R. & Comminion's reled evddon AttorneyForucensee: Ernest L Butler. g y *'",a"" pq Blake.Esq., Shew Pittman.Potts and g_, g bldem w' 8, Docket No.56-414. Donald C. Cook Nuclear Plant. Unit No.2, E=rriaa of no signifte==t hasards capsideration are contained in a Safety Evaluation Zoco/PublicDocumentRoom location: Ceorge S. Houston Memorial County, MI dated April 3,1987.
Ubrary,212 W. Burdeshaw Street. Date of Applioption for aumandment: - Afsorneyforuceness Corald Dothan. Alabama 36303. March 30."1987. Charnoff. Esq, Shaw.pittman. Potts and NRCProject Director:LesterS. Brief description of amandnent % Ttowbridgo. 2300 N Street. NW.,
Rubenstein. amendment revises the Technical Washington. DC 20037.
l Cleveland Electric illundasting Co Specification on a one. time basis to Zoco/PublicDecirment Room Duquane Ught %,OMo Ebn allow the weights of three new a baskets location: University of Toledo Ubrary.
Co., Pennsylvania Power Co., Toledo to be substituted for three adjacent row Documents Department. 2001 Bancroft i Edison Co Dodet No.56-440. Perry 9 baskets in the ice condenser. Avenue. Toledo. OH 43eos.
Date ofIssuance: April 3.1987.
l l
NuclearPowerPlant UnitNo.1 Lake Effective Date: Apn'l 3.1987.
NRCProfectDirectorr }ohn F. Stolz. l County, OH Deted at Bethuda. Maryland. this 10th day Amendment No. 90.
Date ofApplicationforamendment: Facility Opentim baneeNo.NPR- ofA Pril 1**7 March 4.1987, se supplemented on 74: Amendment revised the Technical For the Nuclear Regulatory r*=h .
March 19,1987. Specifications. Sessun A.Varge.
Briefdescription of amendment & Public commente requestedas to grector. Dirision ofReactorProjecto-4/71.
amendment changes the maximum proposedno senificanthasard' isolation time allowed by the Technical considemtion:No. (FR Doc.s7-es32 Filed Mmm)
Specifications from 50 seconds to 20 ne Commission's related evaluation '*'""****'"***
l seconde for operation of the Reactor of the amendment is contained in a Core Isolation Cooling (RCIC) system Safety Evaluation dated April 3.1987.
inboard cont ain==nt isolation valva. It AtrorneyForLcensee: Gerald also deletes from the Technical Charnoff. Esquire.Shaw.Pittman Potts Specifications the losd represented by and Trowbridge.1aOO M Street. NW the valve's direct-current (DC) opereter Washington. DC 20038.
and identification of the motor control LocalPublic Document Room center through which DC power is location:Maude Preston Palenske supplied to the operator. hse changes Memorial Ubrary. .
are being made in reladon to conversion 300 Market Street. St. Joseph.
of this normally-closed.DC motor Michigan 40085.
operated valve to be normally-open with NRCProjectDirector B.J.
en alternating-current (AC) operator. Youngblood. -
DateofIssvonce AprilL1987 .g.gg, ygg,,, g ,,m cg,,g,g .
E F te 1.1987.
Bladn4 A Dodd No. *
- ' D*"'*** N"*I**' h**' ****I**'
Focility Openting Ucense No.NPF-5& Amendment revised the Technical Unit No.1, Ottawa County, OR Specifiutkons. Date ofApplicationforamendme.2:
Public comments requested as to March 30.1987 (telecopied), as proposed no sigmficant hasards anafirmed March 31.1987.
- - _ _ _ _ _ _ _