ML20009C510
| ML20009C510 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/10/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | BOSTON EDISON CO. |
| Shared Package | |
| ML20009C504 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8107210172 | |
| Download: ML20009C510 (10) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION-lit the Matter of
)
Docket No. 50-293
)
BOSTON EDIS0N COMPANY
)
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(Pilgrim Nuclear Power Station,
)
Unit 1)
)
)
ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES Boston Edison Conpany (the licensee) is the holder of Facility Operating License No. OPR-35, which authorizes the operation of tie Pilgrim Nuclear.
Power Station, Unit 1, (the facility) at steady-state reactor power levels not in excess of 1998 megawatts thermal.
The facility is a boiling water reactor located at the licensee's site near Plymouth, Massachusetts.
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II.
Following the accident at Three Mile Island Unit No. 2 (TMI-2) on March 28, 1979, the Nuclear Regulatory Comission (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 additicnal protection for the operation of nuclear facilities n
8107210172 010710 PDRADOCK05000g_
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. 7590-01
- based on the experience from the accident at TMI-2 and the official studies and investigations of the accident. The staff's proposed requirenents 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 suamitted by the ifcensee, scheduled to be completed on or before June 30, 1981 (see the Attachment to this Order). NUREG-0737 was transmitted to eacn licensee and applicant by an NRC letter from my office dated October 31, 1980, which is hereby incorporated by reference.
In that letter, it was indicated that although the NRC staff expected each requirement to be implemented in accordance wi+h 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 submitta,ls dated December 15, 1980, January 5 and 22, and February 11 and 27,1981 and the references stated therein, which are incorporated herein by reference, committed to complete each of the actions specified in the Attachment. The licensee's submittals included a modified schedule for submittal of certain information. The staff has reviewed the licensee's submittals and determined that the licensee's modified schedule is acceptable based on the following:
.. 7590-01 The licensee's schedule for submittal of information in some instances does not meet the staff's specified submittal dates. Most of the information requested by the staff describes how the licensee is meeting the guidance of NUREG-0737. Therefore, this deferral of the licensee submittal will not alter the implementation of plant modifications. Therefore, plant safety is not affected by this modification in schedule for she submittal of information.
I have determined that these commitments are required in the interest of public health and safety, and therefore, should be confirmed by ORDER.
IV.
Accordingly, pursuant to Sections 103,1611,1610, and 187 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED EFFECTIVE IMMEDIATELY THAT the licensee shall comply with the following conditions:
The licensee shall satisfy the specific requirements described l
in the Attachment to this Order (as appropriate to the licensee's facility) as early as practicable but no later than 30 days after the effective date of the ORDER.
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, 7590-01 Y.
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. Nuclear Regulatory Commission, Washington, D.C.
20555. A copy shall also be sent to the Executive Legal Director'at the same address.
If a hearing is requested d
by a person other than the licensee, that oerson shall describe, in accordance with 10 CFR 2.714(a)(2), the nature of the person's interest and the manner in which the interest is affected by this Order. A REQUEST FOR HEARING SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS OF 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 shall be whether, on the basis of the information set forth in Sections II and III af this Order, 'the licensee should comply with the conditions set forth in Section IV of this Order.
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. 7590-01 D
This request for information was approved by OME under clearance number 3150-0065 which expires June 30, 1983. Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management,
- Room 3208, New Executive Office Building, Washington, D. C.
This Order is effective upon issuance.
~0R THE NUCLEAR REGULATORY COMMISSION dlb I,
(b Earrell G. Eiseahut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda, Maryland this 10 day of July-1981
Attachment:
NUREG-0737-Requirements V
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.'NUREG 0737 REQUIREMENTS Imol/ Doc-Item Ti tl e '
Applicability SpeciLifRecairement Suba Due Dater I.A.l.1-
.STA ALL (a) PrJvide STA' coverage by 1/1/81 degreed indiviowals (cr equivalent),_ trained to licensee's orogram.
(b) Submit description of 1/1/81 current training procram and demonstrate compliance with 10-30-79 letter.
(c) Submit description of long 1/1/81-term training program.
I.A.:.1
-Reacto-Goerator ALL Submit cescription of and imple-3 /1.,3c Qualification ment Upgraded Training Program.
1.C.1 Accident Procedures ALL (a) Submit reanalyses of inade-1/1/81 quate core cooling anc propose guidelines for emergency procedures. 0R propose schedule and justify delays.
(b) Submit reanalysis of 1/1/81 transients and accidents for emergency procedures, OR propose schedule and justify delays.
I.C.5 Feedback of ALL Implement procedures for 1/1/81 Operating Experience feedback of operating experience (no documentation sutrittal is required).
I.C.6 Correct Performance ALL Impleinent ::cocedures to verify 1/1/81 or Operating Activities correct performance of coerating activities (no documentation submittal is requirad).
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J Impl/Occ item.
Title Aopl4cability Specific Recuirement Subm Due Dates II.B.2 Shielding ALL (a) Have available' design 1/1/31-details for vital area modifications.
(b) Submit techtical
'l/1/81 deviations to staff po s i tio,n s.
II.B.3 Post-Accident ALL Submit description 1/1/81
.Samoling of deviations from staff positions.
II.B.4 Training to ALL.
'(a) Have available for 1/1/81 Mitigate Core review a training Damage program for mitigating core damage (no documen-tation submittal required)
(b) Implement training 4/1 /81 program (no documentation submittal required).
_II.0.1
10/1/80 (BWRs)-
RV/SRV's (b) Submit oualification program for PWR's block valve.
1/1/S1 (PWRs)
II.E.1.2 Aux Feed PWRs (a) Submit final design and I/1/81 Initiation documentation on safety and Flow grade flow indication.
(b) Submit final design and 1/1/81 documentation on safety grade flow initiation.
II.E.4.2 Containment ALL (a) Submit documentation 1/1/81 asolation justifying minimum contain ment pressure setpoint for isolation of non-essential penetrations.
(b) Submit statement that 1/1/81 purge valves net meetinc~
CSB 6-c (or interim posi-tion)are seale.d and verifi-cation is performed every 31 days.
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Imol/ Doc Iten-Title Aeolicability Specific Petirement Subn Oue Dates
.l II.P.it Post-Accident-ALL a.
For noble gas monitor 1/1/81 Monitoring and. Iodine / particulate sampling and analysis-submit description and justification for deviations from staff requirements.
b.
Have available the 1/1/81 final design infor-mation for noble gas monitor and iodine /
particulate sampling and analysis.
II.F.2 Inst. for Inadequate ALL Submit a report detailing _ the-1/1/81 Core Cooling planned instrumentation syste for monitoring inadequate core cooling.
-II.K.2.10
-Antic. Trio on B&W Submit final design for 1/i/81 LGFW and TT anticipatory trio as described in NUREG 0737.
II.K 2.13 Thermal Mechanical B&W Submit report on effects 1/1/81 Report of Hi Prcssure Injection on vessel integrity for SB LOCA with no Aux Feedwater.
II.K.3.2 P0HV/SV Failures PWR Submit report on 55 LOCA 1/1/S1 and probability of failure of PORV/SV/RV.
~!I.K.3.3 SRV/SV Failures ALL Submit report (historical 1/1/81
& Challenges and annually thereafter) of SRV/SY failures and challenges.
II.K.3.7 PORY Ocening B&W Submit report'on the 1/1/81 Probability probability of a PORV opening during an over-pressurization transient.
II.K.3.9 PIO Controller Selected W Modify the Proportional 12/1/80
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Modification plants Integral Derivative Controller (as reccirended by 'd).
Advise NPC wnen modification is completed.
II.K.3.12 Anticipatory Trip
'i Submit confirmation of 1/1/81 on Turbine Trip Anticipatory Tr1p.
If not currently imolemented, submit modification design and schedule for implementation.
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4-Impl/Dac Item' Title Acolicability Soecific Recuirement Sub: Dans 11.K.3.13 Separation of BWRs w/HPCI/RCIC Submit results of 1 /1 /31 HPCI/RCIC evalcation and proposed
' Initiation Levels; modification as appropriate.
Auto Restart of-RCIL II.K.3.15 Reduce Challenges SWR Sub=it report on actions 4/1 /81 to RV's planned to reduce RV challenges.
II.K.3.17 ECCS System Outages ALL Submit report on ECCS 1/1 /51 outages and propose changes to reduce outages.
II. K. 3.18 ADS Logic BWR Submit report of feasibility 4/1/El Modifications of ADS system logic changes to eliminate need for manual actuation.
II. K. 3. 21 CSS /CPCI Restart SWR Submit report of evaluation, 1/1/El proposed modifications and analysis tf satisfy staff positions.
1:.K.3.22 ROIC Suction SWR w/RCIC Implement procedures and 1/1 /51 document verification of this change.
II.K.3.27 Ccmmon Reference BWR Implement change end submit 1/1/51 for M 0 Level Instruments documentation of changes.
2 II.K.3.29 Isolation SWR w/ICs Submit evaluatien of I.C.
4/1 / 81 Condenser performance.
Ferfermance II.. 3.30 55 LOCA Methods ALL Submit outline of program 11/15/30 for redel.
II.K.3.a4 Fuel Failure BWR Submit evaluatien te verify 1/2/81 no fuel failure.
II.K.3.a5 Manual Depressur-BWR Submit evaluation on other 1/1/31 i:ation than ACS method for depressuritation.
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Impi/OSc-
- ::e-Tit 3 Applicability.
tSpectfic Requirement,
' Subm Due Dates
- :-II!.0.3.3 Impecyed inplant'
. ALL-Have available means to -
1/1/g1
. Iodine,% nitoring accurately measure airborne.
radiciodine -inplant during an accident.
! ! !. D. '3. 4 Control-Room Habitability ALL.
'. a. Submit control room 1/1/81 habitability evaluation in forma tion, b.
Subruit modifications 1/1/81 necessary to assure' CR i
' habi tabili ty with a '
schedule for completion.
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