ML19347F105
| ML19347F105 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/29/1981 |
| From: | Donoghue D NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Hill J OFFICE OF MANAGEMENT & BUDGET |
| References | |
| NUDOCS 8105150248 | |
| Download: ML19347F105 (35) | |
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WJBesaw R/F TIDC R/F gMB r/f Mr. Jeff Hill Office of Management and Budget;,.
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Dear Mr. Hill:
wt In accordance with the Pape worlo Reduction Act of.1980 (P.L.. S6-511), the
.s Nuclear Regulatory Comission js, submitting IMI Action Plan Requirements <.
for Operating Huclear Power Plants, and. related orders for your. review.
This submittal is provided in ao'cordance with, s 3507.
.Your approval is requested by May 1,1981 in order. that.the Comission may issue Orders in sufficient time to allow licenseps.to, proti.de required data by June 30,.1981.
Please note that the SF-83 data 'ilndicates burden has been. discovered to be in tne base inventory of benctra,rA hours. transferred from.the General Accounting Office.
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.s The following statement will be 'added as. the, final. paragraph.in all orders or.
other comunications relevant to: the TNI. Action Plan that Jalate to the.
infomation collection. requirements:... _. s.....
"The infomation collectik requirements. contained in..this order / letter..
have been approved by the,0ffice of. Management and Budget,.0ME approval.
Number:
In addition to ur Clearance Officer.. Nr.. Jack Roe of the Nuclear Reactor Regulation staff is available 40. assist you,.in.your. review Your cooperation and prompt actio' n.on.this request..is appreciated.,
s, Sincerely, s.
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Daniel J. Donoghue, Director Office of Administration l
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UNITED STATES
' ' I 3 ) w ~%j NUCLEAR REGULATORY COMMISSION wAsmNGTON, D. C. 20555 APR 2 91981 Mr. Jeff Hill Office of Management and Sudget Room 3228 New Executive Office Building Washington, D.C.
20503
Dear Mr. Hill:
In accordance with the Papenvork Reduction Act of 1980 (P.L.96-511), the Nuclear Regulatory Comission is submitting TMI Action Plan Requirements for Operating Nuclear Power Plant.i and related orders for your review.
This submittal is.provided in accordance with I 3507. Your approval is
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requested by May 1,1981 in order that the Comission may issue Orders in sufficient time to allow licensees to provide required data by June 30, 1981.
Please note that tne SF-83 data indicates burden has been discovered to be in the base inventory of benchmark hours transferred from the General Ac:cunting Office.
The following statement will be added as the final paragraph in all orders or otner comunications relevant to the TMI Action Plan that relate to the information collection requirements:
"The information collection requirements contained in this order / letter have been approved by the Office of Management and Budget, OMB approval Number:
In addition to cur Clearance Officer, Mr. Jack Goe o# the Nuclear Reactor Regulation staff is available to assist you in your review.
Your cooperation and prcmpt action on this request is appreciated.
Sincerely, 1
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. o, SUPPORTING STATEMENT FOR TMI ACTICN PLAN REQUIREMENTS FOR OPERATING NUCLEAR PCWER PLANTS AND RELATED N,'C CRDERS t
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SUPPORTING STATEMENT 1.
JUSTIFICATION Following the accident at Three Mile Island Unit 2 (TMI-2) on March 28, 1979, the Nuclear Regulatory Commission (NRC) staff developed a number of require-ments that must be implemented on operating reactors and on plants under construction. These requirements include Operational Safety, Siting and Design, and Emergency Preparedness and are intended to provide substantial additional protection in the operation of nuclear facilities based on the experience from the accident-at TMI and the official studies and investi-gations of the accident. The staff's proposed requirements and schedule for implementation are set forth in NUREG-0737, " Clarification of TMI Action Plan Requirements." NUREG-0737 was transmitted to each licensee and apolicant by NRC letter from Darrell G. Eisenhut, Director, Division of Licensing, Office of Nuclear Reactor Regulation, dated October 31, 1980.
The information which is required to be submitted by NUREG-0737 and related CRDERS will be reviewed by the NRC staff to ensure that the TMI Actiot Plan Requirements are properly imolemented. The information recuested is available only from the individual licensees.
In those cases where parts of tne information has been submitted to the NRC previously, those parts may be referenced and re-submittal is not required.
2.
DESCRIPTION OF SURVEY PLAN
- These ORDERS will be addressed to 65 operat.ng nuclear power plants (mailing list maintained by NRC). The information requested will be reviewed to determine compliance with NRC requirements.
Failure to provide the requested information would be in violation of Commission ORDERS and, therefore, subject to civil penalty.
l This is not a survey; therefore, there is no survey design.
3.
TABULATION AND PUBLICATION PLANS i
Information requested by these ORDERS will not be tabulated for the purpose of publication. The staff will perform review of the information to determine compliance with NRC requirements. On comoletion of that review, a Safety Evaluation Report on each issue will be sent to the
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licensee and made available to the public.
4.
TIME SCHEDULE FOR CATA COLLECTION AND PUBLICATION Information requested by these ORDERS will not be tabulated for the purpose of publication. The information requested by these ORDERS is due prior to June 30, 1981. One half of the Safety Evaluation Reports will be published by Decemoer 1981 and the remaining one half will be published by December 1982. Any Amendments to SER's will be published by June 30, 1983.
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CONSULTATIONS CUTSIDE THE AGENCY
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Coments had been previously solicited by letter dated Septemcer 5,1980, from the public and from the affected utilities in relation to these requirements and their implementation schedule. These coments were considered in arriving at the implementation schedule contained in these ORDERS.
6 ESTIMATION OF RE pCNDENT REPORTING BURDEN ' ' ' ' '
Based on NRC experience with requests of this nature, the reporting burden on licensees is estimated to be 6.15 man years per licensee.
7.
SENSITIVE QUESTIONS NA 8.
-E5TIMXTE OF COST 7e rEDERAL'60VERNMENT These CRDERS do not constitute a survey. Total cost to the government of this overall licensing action will be 20 professional man years and
$1.5M in technical assistance funds.
9.
PRACTICAL UTILITY These ORDERS provide a legal basis for enforcement of post-TMI requirements.
These requirements have been under development for some time, and the @ttes
_., for submission _of the required infonnation are practicable _and.achiavabje.,.
NRC has programed the necessary resources to review this infonnation.
Several contractors have been retained to review some of the information.
- 10. NECESSITY The primary mission of the Nuclear Regulatory Comission is to ensure that the design, construction, and operation of nuclear power plants does not endanger the health and safety of the general public. Extensive investi-gations and reviews following the accident at Three Mile Islard indicated the necessity for additional requirements for nuclear power plants. A number of these requirements were ordered by the Comission and was implemented by January 1,1980.. The purpose of these ORDERS is to issue the requirements due for completion by June 30, 1981. The issuance of these requirements including the submittal of certain evaluations and reports is vital to the NRC's mission to protect the health and safety of the public. For some of the requirements issued by these ORDERS, infonnation concerning proposed modifications is required to be submitted so that NRC approval can be granted prior to the modifications being implemented at the nuclear power plants. For the othi require-ments, infonnation is required to be submitted in order for the NRC to verify the nuclear power plant licensee's compliance with the requirements.
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- 11. COPY REQUIREMENTS These ORDERS require one copy of the infonnation submittals listed in the i
attachment.
- 12. RECCR0 RETENTION The information submitted by the licensees will be retained for the duration of the facility operating license nonnally at least 40 years.
- 13.
SUMMARY
REPORTING REQUIREMENTS See attachment.
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$.... I Sc:ket Nos. 50-277 and 50-278 Mr. Edward G. Sauer, Jr., Esquire Vice President and General Counsel Philadelphia Electric Ccmpany 2301 Market Street Philadelphia, Pennsylvania 19101 Cear Mr. Bauer:
The Commission has issued the enclosed Order confirming your commitments for 24~ related requirements for the Peach 3ottom Atomic Power Station, Units
':cs. 2 and 3.
This Order is based on your letter dated December 22, 1980, as revised by letter dated February 20, 1981, to implement those requirements se-forth in NUREG-0737 for which the staff requested completion before
. une 30,1981. Explicit statements of these requirements are set forth in
-he Attachment to the Order.
is the Ccmmission's intent in issuing this Order to encourage the comple; ion Hovaver, certain of
- f items consistent with the staff's recommended schedule.
jour procosed schedule exception; are acceptable. Therefore, you should proceed
.i th implementation of these itr.s in accordance with your proposed schedule.
Your procosed technical and schedule exceptions for other items contained in 1U?.E3-0737 will be the subject of future correspondence.
A ecpy of this Order is being filed with the Office of the Federal Register for publication.
A Sincerely, John F. Stolz, Chief Operating Reactors Branch da Division of Licensing En:losure:
Order cc w/ enclosure:
See next page
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IO UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter cf
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Dockets Nos. 50-277
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and 50-278 PH!LACELPHIA ELECTRIC CCMPANY, ET AL )
)
(Peach Bottom Atomic Power Station, )
Units Hos. 2 and 3)
)
)
ORDER CONFIRMING LICEuSEE CCMMITMENTS ON POST-TMI RELAl ; ISSUES The Philadelphia Electric Company (the licensee) and three other co-owners are the holders of Facility Operating Licenses Nos. OPR-44 and DPR-56, which authorize the operation of the Peach Bottom Atomic Power Station, Units Nos.
2 and 3 (the facilities) at steady state reactor power levcis not in excess of 3292 megawatts thermal for each unit. The facilities are boiling water reactors located at the licensee's site in York County, Pennsylvania.
II.
Following the accider t at Three Mile Island Unit No. 2 (TMI-2) on March 28, 1979, the Nuclear Regulatory Commission (NRC) staff developed a number of proposed requirements to be implemented on operating reactors and on plants under construction. These requirements include Operational Safety, Siting and Design, and Emergency Preparedness and are intended to provide substantial additional protection for the operation of nuclear facilities e
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.. cased on the experience from the accident at TMI-2 and the official studies a-d investigations of the accident. The staff's proposed requirements and schedule for implementation are set forth in NUREG-0737, " Clarification of TMI Action Plan Requirements." Among these requirements are a number of items, consisting of hardware modifications, administrative procedure irplementation and specific infonnation to be submitted by the licensee, scheduled to be compTete on er before June 30,1981 (see the Attachment to this Order). NURE3-0737 was transmitted to each licensee and applicant by NRC letter fecm Darreil G. Eisenhut, Director, Division of Licensir.g, Office of Nuclear Reactor Regulation, dated October 31, 1980, which is hereby incorporated by reference. In his letter, Mr. Eisenhut indicated t,at although the NRC staff expected each recuirement to be implemented in accordance with the schedule set forth in NUREG-0737, the staff w:uld consider licensee requests for relief frca staff proposed require-
. Tents and t.1eir associated implementation dates.
A III.
Twe l_icensee's subnittals dated December 22, 1980, and February 20, 1981, wtich are incorporated herein by reference, committed to implement each c' the actions soecified in the Attachment. The licensee's submittals 1 cluded a codified schedule for submittaT of certain infornation. The staff has reviewed the licensee's submittals and determined that they are a:ceptable based on the following:
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pq q 7" hib The licensee's schedule for submittal of certain information is within three months of the staff's specified submittal dates. Since the nature of the infornation to be submitted is principally a description of deviations from the staff position, the licensee's proposed schedult for submission satisfies the intent of the requirement. Deferral of the licensee submittal for three months will not alter the implementation of plant modifications. Therefore, plant safety is not affected by this relaxation in schedule.
It has been determined that the licensee's commitnents should be confirmed by ORDER.
IV.
Accordingly, pursuant to Sections 103,1611,1610, and 182 of the Atomic Energy Act of 1954, as amended, and the Ccemission's regulations in 10 CR Parts 2 and 50, IT IS ttERE3'r ORDERED THAT the licensee shall comply with the following conditions:
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The if censee shall satisfy the specific requirements described in the Attachment to this Order (as appropriate to the licensee's facilities) as early as practicable but no later than days after the effective date of the Order.
V.
Iny ;erson who has an interest affected by this Order may request a hearing ithin 20 days of the date of publication of this Order in the Federal
- egister. Any request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Comnission, Washington, D.C.
20555. A copy shall also be sent to the Executive
- egal Director at the same address. If a. hearing is requested by a person other than the licensee, that person shall describe, in accordance with 10 CFF 2.714(a)(2), the nature of the persqn's interest and the manner in N
hich the interest is affected by this Order.
~.f a hearing is requested by the licensee or other persons who hava an interest affected by this Order, the Commission will issue an Order designating the time and place of any such hearing.
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' If a hearing is held concerning this Order, the issue to be considered at the hearing shall be whether, on the basis of the information set forth in Section II and lit of this Order, the licensee should comply with the condi-tions set forth in Section IV of this Order.
This Order shall become effective upon expiration of the period within which a hearing may be requested, or, if a hearing is held on the date specified in an Order issued following further proceedings on this Order.
FOR THE NUCLEAR REGULATORY CCMiiISSION Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this day of 1981
Attachment:
NUREG-0737 Requirements O
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MD ! U ATTACHMENT UR"klI NUREG 0737 REQUIREMENTS Imol/Coc Item Title Acclicability Scecific Recuirenent Subm Due Cates I. A.1.1 STA ALL (a) Provide STA coverage by 1/1/31 degreed individual s (or equivalent), trained to licensee's program.
(b) Submit description of 1/1/31 current training program and comaare with 10-30-79 letter.
(c) Submit description of long 1/1/91 term training program.
I.A.I.T Reactor Ccerator ALL Sucmit description of Upgraced 3/1/3C Qualification Training Program, I.C.1 Accident Frocedures ALL (a) Submit reanalyses of inade-1/1/31 quate core cooling and propose guidelines for emergency procedures, OR propose schedule and justify delays.
(b) Submit reanalysis of 1/1/81 transients and accidents for emergency procedures, CR propose schedule and justify delays.
I.C.5 Feedback of ALL Imolement procedures for 1/1/31 Ocerating Exoerience feedback of operating procedures (no documentation is recuired).
I.C.6 Correct Dorformance ALL ImoTement orecedures to verify 1/1/81 or Operating Activities correct performance of operating activities (no documentation is required).
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2-Impl/Coc Item Title Acolkability 5,cecific Recuirement Sabm Due Jates II.3.2 Shielding ALL (a) Have available design 1/1/31 details for vital area modifications.
(b) Submit technical 1/1/S1 deviations to staff positions.
II.3.3 Post-Accident ALL (a) Have availaole design 1/1/81 Samoling details for modifi-cations.
(b) Submit description 1/1/31 of deviations from staff positions.
!!.3.A Training to ALL (a) Have available for 1/1/31 tiitigate Core review a training Oamage program for mitigating core damage (no documen-tation submittal required)
(b) Implement training 471/81 program (no documentation subnittal required).
II.D.1 Perfomance ALL (a) Submit test program 7/1/30 (PWRs?
Testing of (botn BWR/PWR's).
10/1/30 (BWRs)
RV/SRV's (b) Submit qualification program for PWR's block valve.
1/1/31 (PWRs)
II.E.1.2 Aux Feed PWRs (a) Submit final design and I/1/81 Initiation documentation (IEEE 279-and Flow 1971 criteria) on flow indication.
(b) Subnit final design and 1/1/81 documentation (IEEE 279-1971 criteria) on flow initiation.
II.E.4.2 Containment ALL (a) Submit documentation 1/1/81 Isolation justifying minimum contain-ment setpoint for isolation of non-essential system.
(b) Submit statement that 1/1/31 purge valves not meeting CSB 6-4 tre sealed and verification is performed e
every 31 days.
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DRAff 3-I Impl/Occ Item Ti tl e Acolicability Soecific Requirement Su:m Cue Cates II.F.1 Post accident ALL For noble gas monitor and 1/1/81 Monitoring Iodine / particulate monitor, submit description and justification for deviat1ons from staff requirements.
II.F.2 Inst. for Inadequate ALL Submit a report detailing 1/1/8i Core Ccoling planned actions for an instrumentation system to detect inadequate core cooling.
II. K. 2.10 Antic. Trio on B&W Submit final design for 1/1/S1 LCF'd and TT antici;atory trip as described in NUREG 0737.
II.K.2.13 Thermal Nechanical B&W Submit re;crt on effects 1/1/31 Repcet of Hi Pressure Injection on vessel integrity for SB LOCA with no Aux Feecwater.
II.K.3.2 PORV/SV Failures PWR Submit report on SB LOCA 1/1/S1 and probability of failure of PORV/SV/RV.
II.K.3.3 SRV/SY Failures ALL Submit recort (historical 1/1/81
& Challenges and anneally thereafter) of SRV/SV failures and challenges.
II.K.3.7 PORY Ccening B&W Submit report on the 1/1/e1 Pro bab
II.K.3.9 PID Centroller Selected W, Modify the Proportional 12/1/80
_ Modification plants Integral Derivative Controller (as recomrnended by W). Advise NRC when modification is completed.
II.K.3.12 Anticipatory Trip W
Submit confirmation of 1/1/81 on Turbine Trip Anticipatory Trio.
If not currently implemented, submit modification design and schedule for implementation.
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4 Impl/ Doc Item Titl e Acclicability Scecific Recuirement Sub= Cass II.K.3.13 Separation of BWRs w/HPCI/RCIC Submit results of 1 /1 /31 HpCI/ECIC evaluation and proposed Initia:fon Levels; modification as appropriate.
Auto Restart of RCIC II. K.3.' 6 Reduce Challenges BWR Sub=it repcrt en actiens 4 /1 /31 to RV's planned to reduce RV challenges.
II. K.3.17 ECC5 Systm Outages ALL Su bit report en ECOS 1/1 / 31 cutages and prepose changes
- w reduce ou* ages.
II. K.3.18 ACS Logic 5'd Submit re;crt of feasittlity 4/1/El Modifica icns cf ADS system logic changes to eliminate need for manual actuation.
II.K.3.21 CI5/CpCI Restar:
SWR Submit reper: of evaluation, 1 /1 /51 preposed modifica:icns and analysis tf satisfy staff positions.
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II.K.3.22 RC*C Suetien SWR w/RCIC Implement procedures and 1/1/E1 document verification of this change.
II.K 3.27 Ce.. ~n Reference BWR
!=plement change and sub=it i/1 / 31 for H;0 Level Instrue:nts cocumentation of changes.
II. K.'3. 23 Isolatien 3'd w/ICs Submit evaluatien cf I.C.
4 /1 / 51 Condenser perfor=ancc.
perfor.ance II.K.3.30 53 LCCA Metneds ALL Submit cuttine cf program 11/15/30 for medel.
II.K.3.a4
' Fuel Failure BWR Submit evaluatien te verify 1/,1/a1 no fuel failure.
II.K.3.45 Manual Depressur-SWR Submit evaluation en other
' i /1 / 51 ication than ACS method for depressurication.
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- en Title Acolicability Scecific Requirement Sgbm Due Cates III.D.3.3 Impetved Inolant AL,,
(a) Have available descrip-1/1/81 Iodine. Monitoring tion for fodine samoling (b) Submi info rma tion /
1/1/81 justification for deviations from plant position.
III.O.3.4 Control Rocm Habitability ALL Submi: resul ts of CR Habita-1/1/31 bility Study.
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wi ul Occket No. 50-255 Mr. David P. Hoffman Nuclear Licensing Administrator Consumers Power Company 1945 West Parnell Road Jackson, Michigan 49201
Dear Mr. Hoffman:
The Comission has issued the enclosed Orders for the Palisades Plant.
The first Order confinns your comitments on TNI related requiremerits except for Item I.C.6, " Guidance on Procedures for Verifying Correct Perfarnance of Operating Activities." The second Order instructs your company to meet the requirements of Item I.C.6 in a timely manner.
These orders are based on your letter dated December 19, 1980, to implement those requirements set forth in NUREG-0737 for which tne staff requested completion before June 30, 1981. Explicit statements of these requirements are set forth in the Attachment to the first Order.
It is the Comission's intent in issuing these Orders to encourage completion of items consistent with the staff's recomended schedule.
However, certain of your proposed schedule exceptions are acceptacle.
Therefore, you should proceed with implementation of these items in accordance with your proposed schedule. Your proposed technical and schedule exceptions for other items contained in NUREG-0737 will be the subject of future correspondence.
E copy of these Orders is being filed with the Office of the Federal Register for publication.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch 15 Division of Licensing Eny.1osure:
Orders CC:
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Unh UNITED STATES OF M' ERICA NUCLEAR REGULATCRY COMMISSION In the Matter of
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Docket No. 50-255
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CONSUMERS PCWER COMPANY
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(Palisades Plant)
)
ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES I.
Consumers Pcwer Company (the licensee) is the holder of Facility Operating License No. DPR-20 which authori:es the operation of the Palisades Plant (the facility) at steady-state pcwer levels not in excess of 2530 megawatts therm 1.
The facility is a pressurized water reactor (PWR) located at the licensee's site in Van Buren County, Michigan.
II.
Following the accident at Three Mile Island on March 28, 1979, the Nuclear Regulatory Commission (NRC) staff developed a number of proposed require-ments to be implemented on operating reactors and on plants under construction. These requiremer.ts include Operational Safety, Siting and Design, and Emergency Preparedness and are intended to provide substantial additional protection in the operation of nuclear facilities based on the I.1
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DP&T experience frcm the accident at TMI-2 and the official studies and investigations of the accident. The staff's proposed requirements and schedule for implementation are set forth in NUREG-0737, " Clarification of TMI Action Plan Requirements." Among these requirements are a number of items, consisting of hardware modifications, administrative procedure implementation and specific information to be submitted by the licensee, scheduled to be completed on or before June 30,1981 (see the Attachment to this Order). NUREG-0737 was transmitted to each licensee and applicant by NRC letter from Carrell G. Eisenhut, Director, Division of Licensing, Office of Nuclear Reactor Regulation, dated October 31, 1980, which is hereby incorporated by reference.
In his letter, Mr.
Eisenhut indicated tnat although the NRC staff expected each requirement to be implemented in accordance with the schedule set forth in NUREG-0737, the staff would consider licensee requests for relief from staff proposed requirements and their associated implementation dates.
III.
The licensee's submittal dated December 19, 1980, which is incorp? rated herein by reference, comitted to implement each of the actions specified in the Attachment. The licensee's submittal included a modified schedule for submittal of certain information. The staff has reviewed the licen'see's submittal and determined that except for Item I.C.6, " Guidance on Procedures for 'lerifying Correct Perfrance of Operating Procedures," it is acceptible based on the following:
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The licensee's schedule for submittal of certain information is within three months of the staff's specified submittal dates. Since the nature of the information requested is principally a description of deviations from the staff position, the licensee's proposed schedule for submission satisfies the intent of the requirement. Dererral of the licensee submittal for three sonths will not alter the it:plementation of plant modifications. Therefore, plant safety is not affected by this relaxation in schedule.
2.
Item II.D.1, " Performance Testing of Relief V.alves and Safety Relief Valves" of NUREG-0737 includes the requ' ire-ment that PkR licensees should submit by January 1,1981, a qualification test program for PhR block valves. The licensee is a participating member of a PhR Owners Group which is pursuing resolution of valve testing on a generic basis. Although a detailed block valve test program has not been for:ulated, the Owners Group has, initiated a test program for a small number of block valves at the Marshall Steam Station Test Facility. The Owners Group intends to provide a block valve test program in July 1981. The NRC staff has reviewed the licensee's Ei l
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It has been detennined that the licensee's commitments should be confinned by ORDER.
IV.
Accordingly, pursuant to Sections 103,1611,161o, and 182 of the Atcmic Energy Act of 1964, as amended, and the Ccmission's regulations in 10 CFR Parts 2 and 50, IT IS HERESY ORDERED THAT the licensee shall-comply with the following conditions:
The licensee shall satisfy the specific requirements described in the Attachment to this Order (as appropriate to the licensee's facility) as early as practicable but no later than days after the effective date of the
- Order except for Items II.D.1 and I.C.6 of NUREG-0737.
The licensee shall satisfy the requirement for II.D.1 no later than days after the effective date of the Order.
Item I.C.6 will be the subject of a separate Order.
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V.
Any person who has an interest effected by this Order may request a hearing within 20 days of the date of publication of this Order in the Federal Recister. Any request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Comission, Washington, D.C.
20555.
If a hearing is requested by a person other than the licensee, that person shall describe, in accordance with 10 CFR 2.714(a)(2), the nature of the person's interest and the manner in which the interested person is affected by this Order.
If a hearing is requested by the licensee or other persons who have an interest affected by this Order, the Commission will issue an Order designating the time and place of any such hearing.
If a hearing is held concerning this Order, the issue to be considered at the hearing sh11 be mether, on t!e basis of the information set forth in Sections II and III of this 0-der, the licensee should comply with the conditions set forth in Section' IV of this Order.
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FOR THE NUCLEAR REGULATORY COMMISSICN
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Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this day of 5
1981
Attachment:
NUREG-0737 Requirements i
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NUREG 0737 REQUIREM NTS Imol/Occ
!' tem Title Acolicability Soecific Recuirement Sube Due Dates I. A.1.1 STA ALL (a) provide STA coverage by 1/1/S1 degreed individuals (or equivalent), trained to licensee's program.
(b) Submit description of 1/1/81 current training program and comoare with 10-30-79 letter.
(c) Submit description of long 1/1/31 term training program.
I.A.2.1 Reactor 0:erator ALL Submit description of Upgraded 3/1/3C Qualification Training Program.
I.C.1 Accident Pmcedures ALL (a) Submit reanalyses of inade-1/1/31 cuate core cooling and propose guidelines for emergency procedures, OR procose schedule and justify delays.
(b) Submit reanalysis of 1/1/81 transients and accidents for emergency pror.edures, OR procose schedule and justify delays.
I.C.5 Feedback of ALL Imolement procedures for 1/1/31 Operating Experience feedback of operating procedures (no documentation is required).
I.C.6 Correct Performance ALL Imolement crocedures to verify 1/1/81 or Operating Activities correct performance of oceratinc activities (no documentation is i
required).
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h[lb 2-J Impl/Coc Item 7itle Acol4<abil ity Scecific Requirement Sabm Due Cates
!!.3.2 Shielding ALL (a) Have available design 1/1/31 details for vital area modifications.
(b) Submit technical 1/1/S1 deviations to staff positions.
I!.3.3 Post-Accident ALL (a) Have available design 1/1/81 Samoling details for modifi-cations.
(b) Submit description 1/1/31
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of deviations from staff positions.
!!.3.a Training to ALL (a) Have available for 1/1/S1 Mitigate Core review a training Camage program for mitigating core damage (no documen-tation submittal recuired)
(b) Implement training 4/1/31 program (no documentation submittal recuired).
II.D.1 Performance ALL (a) Submit test program 7/1/80 (FWRs,'
Testing of (both SWR /FWR's).
10/1/30 (SWRs)
RV/SRY's (b) Submi: qualification program for FWR's block valve.
1/1/31 (FWRs)
II.E.1.2 Aux Feed FWRs (a) Submi final design and I/1/81 Initiation documentation (IEEE 279-and Flow 1971 criteria) on flow indication.
(b) Submit final design and 1/1/31 documentation (IEEE 279-1971 criteria) on flow initiation.
II.E.1.2 Containment ALL (a) Submit documentation 1/1/81 Isolation justifying minimum contain-3 ment setpoint for isolation of non-essential system.
(b) Submit statement that 1/1/81 purge valves not meeting CSB 6-4 are sealed and verification is performed every 31 days.
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-Item Title Acolicability Scecific Recuirement Summ Due Cates II.F.1 Post Accident ALL For noble gas monitor and 1/1/31 Monitoring Iodine / particulate monitor, sucmit description and justification for deviations from staff recuirements.
II.F.2 Inst. for Inadequata ALL Submit a report detailing 1/1/31 Core Cooling planned actions for an instrumentation system to detect inadequate core cooling.
II. K. 2.10 Antic. Tria on 35W Sutrait final design for 1/1/81 LOP 4 and TT anticipatory tric as described in NUREG 0737.
II. K. 2.13 T'ner a1 Necnanical 35W Submit report on effects 1/i/31 Report of Hi Pressure Injection on vessel integrity for SB LOCA with no Aux Feedwater.
II.K.3.2 PCRV/SV Failures PWR Sucmit report on SB LCCA 1/1/51 and probability of failure of PORV/SV/RV.
II.K.3.3 SRV/SV Failures ALL Submit report (historical 1/1/81 1 Challenges and annually thereafter) of SRV/SV failures and challenges.
II.K.3.7 PCRV Ccening B&W Submit recort on the 1/1/s1 Frobab111ty probability of a PORY opening during an over-pressurization transient.
II.K.3.9 PID Controller Selected W Mocify the Proportional 12/1/80
% dification plants Integral Derivative Controller (as reconcended by W). Advise NRC when modification is completed.
Submit confirmation of 1/1/81 II. K. 3.12 Anticipatory Trip W-Anticipatory Trip. If not on Turbine Trip currently implemented, submit modification design and schedule for implementation.
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Impi/Dec Item Title Accifcability Scecific Recuirement Sutm Cats i
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II.K.3.13 Separation of BWRs w/HFCI/RCIC Submit results of 1 /1 /31 HpCI/RCIC evalcation and proposed Initiation Levels; modification as appropriate.
Auto Restart of RCIC II.K.3.15 Reduce Challenges SWR Submit report en actions 4/1 /31 to RV's planned to reduce RV challenges.
II.K.3.17 ECCS System Cutages ALL Submit report en ECCS 1/1 /51 cutages and prepose changes to reduce cutages.
II.K.3.18 ADS Logie BWR Submit repcrt cf w F.bility 4/1 / 51 Mcdifica:icns of ADS system logic changes to eliminate need for manual actuation.
II.K. 3. 21 CS3/CpCI Resta-:
BWR Submit report of evaluation, 1 /1 / 31 p cocsed modifications and analysis t1 satisfy staff positions.
1~.K.3.22 RCIC Suction SWR w/RCIC
!=plement procedures and "
1/1 / 51 document verifica icn of this change.
II.K.3.27 Com=cn Reference BWR
!=ple ent change and sub=it 1/1 / 31 for H O Level Instrue nts documentation of changes.
2 II.K.3.2; Isciation SWR w/ICs Submit evaluation cf I.C.
4/1 / 51 Condenser pe 'er: ance.
per'cr=ance II. K. 3. 30 55 LCCA Methods ALL Sub=i outline of program 11/15/30 for model.
II. K. 2. a.'.
Fuel Failure SWR Submit evaluation to verify 1/1/S1 no fuel failure.
II.K.3.45 Manual Depressur-BWR Submit evaluatten en c her 1/1/51 i:ation than ACS method for depressurization.
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III.3.3.3
!.mereved Inolant ALL (a) Have available descrip-1/1/31 Icdine Monitoring tion for iodine samoling (b) Submit information/
1/1/81 justification for deviations frem plant position.
III.D.3.4 Control Recm Habitability ALL Submit results of CR Mabita-1/1/31 bility Study.
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l UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
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In the Matter of
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Docket No. 50-255
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CONSUMERS POWER COMPANY
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(Palisades Plant)
ORDER I.
The Consumers Power Company (the licensee) is the holder of Facility Operating License No. DPR-20 which authorizes the 1fcensee to operate the Palisades Plan'. (the facility) at power levels not in excess of 2530 megawatts ther nal. The facility is a,)ressurized ' ater reactor w
located at the licensee's site in Van Buren County, Michigan.
II.
Following the accident at Three Mile Island Unit (TMI-2) on March 28, 1979, the Nuclear Regulatory Comission (NRC) staff developed a nunter of requirements that must be implemented on operating reactors and on plants under construction. These requirements include Operational Safety, Siting and Design, and Emergency Preparedness and are intended to provide substantial additional protection in the operation of nuclear facilities based on the experience from the accident at TMI and the official studies and investigations of the accident. The staff's proposed requirements
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2-schedule for implementation are set forth in NUREG-0737, " Clarification of TMI Action Plan Requirements." Among these requirements are a number of items consisting of hardware modifications, administrative procedure implementation and specific information to be submitted by the licensee, scheduled to be completed on or before June 30, 1981. NUREG-0737 was transmitted to each licensee and applicant by NRC letter from Darrell G.
Eisenhut, Director, Division of Licensing, Office of Nuclear Reactor Regulation, dated October 31, 1980, which is hereby incorporated by reference. In his letter, Mr. Eisenhut requested pursuant to 10 CFR 50.54(f) confirmation that the implementation dates in NUREG-0737 wculd be met. He also indicated that although the NRC staff expected each requirement to be implemented in accordance with the schedule set forth in NUREG-0737,- the staff would consider Itcensee requests for relief from staff proposed requirements and their associated implementation dates.
III The licensee's submittal dated December 19, 1980, which is incorporated herein by reference, ccmmitted to implement each of the actions scheduled to be ccmpleted on or before June 30, 1981. The licensee's submittal included a modified schedule for submittal of certain information. The NRC staff reviewed the licensee's submittal and determined that the schedule proposed by the licensee was acceptable except for that item 1
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3-identified as I.C.6, ' Guidance on Procedures for Verifyng Correct Performance of Operating Activities." The licensee's revised schedule for the items that the staff found to be acceptable was confirmed by ORDER dated Item I.C.6, " Guidance on Procedures for Verifying Correct Performance of Operating Activities," included the staff's request for the licensee to
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review and revise procedures as necessary to implement the staff's guidance by January 1, 1981. The NRC letter dated October 31, 1980 detailed the guidance which was to be implemented. The guidance of I.C.6, will not provide additional protection in the operation of the facility until the verification procedures are actually implemented at the facility. Therefore, it is important to the safety of the plant for the licensee to implement the guidance of I.C.6 in a timely manner.
Initial implementation of I.C.6 may be achieved by temporary administrative controls allowing more. time for the complete implementation through a formal revision of the plant operating procedures The licensee's letter dated December 19, 1980 stated that a review of the plant procedures against the guidance of I.C.6 was underway. The licensee believed that no or very few changes would be necessary to implement I.C.6; however, no date was cemitted for the completion of the review or imolementation of I.C.S.
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4-Based on a review of the information provi ded by the licensee, the staff has concluded that the licensee has not been responsive to Item I.C.6.
The licensee has not provided a commitment to implement I.C.6 in a timely manner, and the licensee has no': provided an adequate justification for a delay in implementing I.C.6.
IV.
Accordingly, pursuant to Sections 103,1611,1610, and 182 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR Parts 2 and 50. IT IS HERE3Y ORDERED THAT the licensee implement within 30 days after the effective date of this ORDER procedures for verifying correct performance of operating procedur:s.
V.
The 1;censee or any person who has an interest affected by this Order may request a hearing within 20 days of the date of publication of this Order in the Federal Register. Any request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regulation, U.S.
NucTear Regulatory Commission, Washington, D.C.
20555. A copy of the request should also be sent to the Executive Legal Director at the same address.
If a hearing is requested by a person other than the licensee, that person shall describe, in accordance with 10 CFR 2.714(a)(2), that person's interest and the manner in which the interest is affected by
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5-this Order.
If a hearing is held concerning this Order, the issue to be considered at the hearing shall be whether on the basis of the information set forth in Sections II and III of this Order, the license should be modified as set forth in Section IV of this Order.
This Order shall become effective upon expiration of the period within which a hearing :nay be requested, or, if a hearing is requested on the date specified in an Order issued following further proceedings on this Order.
4 FOR THE NUCLEAR REGULATORY CCMMISSION Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this day of 1980.
Attachment:
NUREG-0737 Requirements e
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IMI Action Plan Requirements 4 iutlated E Nc Sect'en 3507 s em'ss ca*
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P00R ORIGINAL-
- 17. Aestract-NeeCs an0 Uses (50 worcs orless)
TMI Action plan imposes reporting and recordkeeping requirements on 65 licensees d ^ oper'ating licenses to provide staff adequate data to perfonn safety reviews of specific deshn ' aspects of nuclear power plants.
l2o Catalog of r cerai Cemestic Assistance 3 cq am Nur-ce-1 S Ritated recort formiss /gtve Ows numcerts1. IRCN(s>.
e N/A mternal agency teport form numcerlsb or symbot(s. None
- 21. smain cusmess er crganizatien
- Yes 3Ao
- 19. Tyce of attectec cuenc (Cneca as many as acem
- 22. Tyce of activity of affected cucaic-mcicate 3-ogit Starca 1: incivreuats or nousencics Incustral ClassQcation 1SC mey 'uc to G - d w t o. check s Mutt:c.e er
.,,.:t 2: state or iccel governments 3 0 farms 4 8 3 a 2Xbusmesses or other,nst. tut.cns 'escect farms 1 23 Br:ef cescriptice :f attected cuclic le 5."retaol grccery stores.'" State education agencies.' "ncuser'cacs en 50 largest SMSA s % Utiliti" Ticensed to operate nuclear power plants ~ 24 Dur:cse (Checs as many as acciy It more than orse. mcicate I26. Cctiecticie method (Check as many as aco!yb preccmmant cy en astensa) 1X1 mast seat-admmsstered t acchcat cn for :enefits 20 ether self-admmistered 2 crogram evaluat:en 3 2 teleoncne mterview 3 0 gerers':urocsa stat'st.cs a perscnalinterview a IXrequia: cry or c:mcaance 5 recorckeecmg requirement-5 cr:g am plann:ng :r ma:aa;ement Recutred retenteen pencd; years 6 resear:n s C otner-cesence-
- 25. Frequency et use
'27.Cettection agent (Checir cne) ? 2XNenrecurnng tD recuesting Cecartment/ Age 9cy Recurnng (cneca as marry as apply!- ll 2 cther FederalCecartment: Agency }, 2 : on occasion e semiannually 3C pnvatecoctracter 3 weekly 7 annually a recordkeeomg requirement 4: mentnfy 50 ciennially ' y,g h.,_ '5 other-desenbe: 5 0 cuarterty 9 cther-cesente; 29 Autncnty for a ;ency for irdermatien costect;cn er '3C. Do you promise conticentialityS rwemamm;-mcicate statute. regulatsen.iucicial cecree. (1/ res. expla,n bases for osedge - % -e e*: ) m succortmg statement.)
- Yes
~' No Atomic Energy Act of 1954, as amended
- nerSI Reorganization Act of 1974 31 "'"' D'C C5'd i"'Cit'en ecueetien mate a new or e
29 cesecccent's cctigatten to recty IChecs as many as apply) beccme cart of an exist:ng PNacy Act system of records, (If yet attacn Feceral 9egsster notice or procosed craft c! t voluntary notsce ) C Yes X2 Ne 2 IXrecuired to Octam or retam beref:t.i.e., Ifceftse 132. C st to eceral Govemme'at Of r 3 0 mandatory-cite statute. nct CFR (attach ccpy el.. ) intermation collecticn or rutemamnq s 13 Mf11 f on statutcry authenty! l CCueLETEITEMS 33 THRU 35 oNLYIF RULEMAK!NG SUOMISSloN 33.0cmciiance costs to the cuche 3 t is there a regulatory smcact
- 35. Is there a statutory or!ucicial analysis attached?
deadime affectmg issuance 7 See Item # 16 g C Yes No C Yes. Enter cate )Q No l CERTIFIC ATtCN SY AUTHORIZED oFFICI ALS SUSMITTtNG RdQUEST-We cef*ify mat the tnformation c0tiection Or rwemanteg sacmitted f:r rev.ew 's,ecessarv ter me or=cer scrmance of me agency s functices mat me or:ocsai re= resents me minimum :ucac cw cen anc Fecerai ::st r l cens. stent..t,,eec. anc is :ensistent witn aconcamie cue and agency ocncy cirectives. Signature a,a titie et a - c oac
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, _. y __ \\ s 1 e _ ( -.-. ( i DISTRIBUTION MAY 6 IS81 TIDC R/F WJBesaw, TIDC g m,- TDorian, ELD JKornbush, PDR Mr. -def' "ill PNorry, ADM Office of Management and Budget.......,................QJDonqghue, ADM Reports Management, Room 3208,,,, n........,.....,... New Executive Office Building,,,,,,..... _......,,.o Ec. 90E Washington. D.C. 20502 p c 4v.s Dear Mr. h p..., ....., ~,. In accordance with Section 350EAf. Pub 1,1c, l.ap S6,-511. af, na-har.11 1980,...... and regulations of the Office of,NanAgaput And.Baiget.I, an enclosingi,................ for the review of OMI copies of AtandATA fom-BA and,.the, Suppor, ting...,,,. s............ Statament covering reporting a04 recordkeeging, requirsments, of NRC Form...........s.,. 171, 171A and 171B. In accordance with NRC's proceh, Ay. staff has made an. independent review of the practical utility and necess.ity, for. the proposed,information collection and we are in concurrence with this proposal. We hava also reviewed for.. duplicatior, and found no similar, regu.irement in..the agency..Therefore, we are transmitting this materialJpr. Appropr.ia?.a OMB, review ansi approval....,, 3 Sincerely, +, Originnl signed by =* R. STEPHEN SCOTT in 6 Dar.iel J. Donochue, Director ,,,., m.., s. Office of Administration
Enclosure:
As stated R00R ORIGINAL i POR [ .TJ . ADM.. . ADM... c"'c' .D DMB. g ... ELD.. ..,hDorian. JKornb h... WJ
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