ML20009C950
| ML20009C950 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/10/1981 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20009C951 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM TAC-12428, TAC-12429, NUDOCS 8107220217 | |
| Download: ML20009C950 (10) | |
Text
7590-01 UNITED STATES OF AMERICA NUCLEAR REGULATORY C0ftMISSION
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In the Matt 0c of
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Docket Nos. 50-282
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and 50-306 NORTHERN STATES POWER COMPANY
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(Prairie Island Nuclear Generating
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Plant, Unit Nos.1 'and 2)
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ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES I.
Northern States Power Company (thc licensee) is the holder of Facility Operating License Nos. OPR-43 and DPR-60, which authorize the operation of Prairie Island Nuclear Generating Plant, Unit Nos.1 and 2, (the facility) at steady-state power levels not in excess of 2815 megawatts thermal. The facilities consist of pressurized water reactors (PWRs) located at the licensee's site in Goodhve County, Minnesota.
l II.
Following the accident it Three Mile Island Unit No. 2 'TMI-2) on March 28, 1979, the Nuclear Regulatory Commission (NRC) staff developed a number of proposed recuirements to be implemc~':ed on operating reactors and on plar'.s under construction. These requirements include Operational Safety Siting and Design, and Emergency Preparedness and are intended t'o provide substantial I
additional protection for the operation of nuclear facilities based on the i
8107220217 810710-l PDR ADOCK 050002Bg l
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p 7590-01 experience from the accident at TMI-2 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." Among these requirements are a number of items, con-sisting of hardware modificitions, 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 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
- 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 implementa-tion dates.
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III.
l The licensee's submittals dated November 20, and December 30, 1980 and January 16, January 30, March 27, and July 6,1981 and the references stated therein, which are incorporated herein by reference, committed to complete l
each of the actions specified in the Attachment. The~ licensee's submittals 1
included a modified schedule for submittal of certain information. The staff has reviewed the licensee's submittals and determined that the licensee's j
modified schedule is acceptable based on the following:
I
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 s
guidance of NUREG-0737. Thera'*re, 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 the 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 103,1611,161o, and 102 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:
i 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 60 days after the effective date of the ORDER.
I 7590-01 4-V.
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 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 interest is affected by this Order. A REQUEST FOR HEARING SHALL NOT STAY THE IMMEDi3TE 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 i
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 of this Order, the licensee should comply with the conditions set forth in Section IV of this Order.
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p 7590-01 5-This request for informatio:. ws: approved by OMB 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.
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This Order is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'mc Robert A. Purple, Deput'y Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesds, Maryland i
this 10th ay of July d
l 1981 l
Attachraent:
l NUREG-0737 Requirements l
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ATTACHMENT NUREG 0737 REQUIREMENTS Impl/ Doc Item Title Applicability Specific Requirement Subm Oue Dates I.A.1.1 STA ALL (a) Provide STA coverage by 1/1/81 degreed individuals (or equivalent), trained to licensee's program.
(b) Submit description off 1/1/81 current training program ar.d demonstrate compliance with'10-30-79 l e tter.
(c) Submit description of long 1/1/81 term training program.
l. A.. l.
Reactor Operator ALL Submit description of and imple-S/1/80 Qualification ment Upgraded Trainirg Program.
1.C.1 Accident Procedures ALL (a) Submit reanalyses of inade-1/1/81 quate core cooling and propose guidelines for emergency procedures, OR propose schedule and justify delays.
(b) Submit reanalysis of 1/1/81 l
transients.ind accidents f
for emergency procedures, OR propose schedule and ' justify delays.
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'.C.5 Feedback of ALL Implement procedures for 1/1/81 Operating Experience feedback of operating experience (no documentation subrittal is i
l required).
I.C.6 Correct Performance ALL Implement procedures to verify 1/1/81 or Operating Activities correct performance of operating activities (no documentation submittal is required).
h Impl/ Doc Item Title Applicability Specific Requirement Sabm Due Dates II.S.2 Shielding ALL' (a) Have available design 1/1/81 details for vital area modifications.
(b) Submit technical 1/1/81 deviations to staff positions.
II.B.3 Post-Accident ALL Submit description 1/1/81 Sampling 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)
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(b) Implement training
~4/1/81 program (no documentation submittal required).
II.D.1 Performance ALL (a) Submit-test program 7/1/80 (PWRs)
Testing.of (both BWR/,PWR's).
10/1/80 (SWRs)
RV/SRV's (b) Submit qualification program for PWR's block valve.
1/1/8? (PWRs)
II.E.1.2 Aux Feed PWRs (a) Submit final design and lil/G1 Initiation documentation on safety and Flow grade flow indication.
(b) Subnit final design and 1/1/81 documentation on safety grad's flow initiation.
II.E.a.2 Containment AuL (a) Submit documentation 1/1/81 Isolation justifying minimum contain-ment pressure setpoint for isolation of non-essential penetrations.
(b) Submit statement that 1/1/81 purge valves not meeting CSB 6-4 (or interim posi-tion)are seale.d and verifi-cation is performed every 31 days.
. Impi/ Doc Sutm Due Dates b
Item Title
~ Applicability Specific Requirement I I '. F.1.
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 repcet detailing the 1/1/81 Core ~ Cooling planned instrumentation systen for monitoring inadequate core cooling.
_ II.K.2.10 _
Antic. Trip on B&W Submit final design for 1/1/81 LOFW and TT anticipatory trip as described in NUREG 0737.
II.K.2.13' Thermal Mechanical B&W Submic report on effects 1/1/81 Report of Hi Pressure Injection on vessel integrity for SB LOCA with no Aux Feedwater.
.II.K.3.2 PORVf5V Failures PWR Submit report on SB LOCA 1/1/S1 and probability of failure of PORY'SV/RV.
II.K.3.3'
'SRV/SV' Failures ALL Submit report (historical 1/1/81
& Challenges and annually thereafter) of SRV/SV failures and challenges.
~. II. K. 3. 7
.PORY' Opening B&W Submit report *on the 1/1/81 Probability probability of a PORV opening during an over-pressurization transient.
II.K.3.9 PID Controller Selected W-Modify the Proportional 12/1/80 Modification plants Integral Derivative Controller (as recommended 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 Trip.
If not currently implemented, submit modification design and schedule for implementation.
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Impl/ Doc s
,, Item Title Applicability Specific Rec.uirement Sub: Dans I..K.3.13 -
Separation off BWRs w/HPCI/RCIC Submit results of 1 /1 /81 iHPCI/RCIC evalcation and proposed Initiation Levels; modification as appropriate.
Auto Restart of RCIC
- II.K.3.16 Reduce Challenges BWR Submit 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 /81 outages and propose changes to reduce outages.
-II.K.3.18 ADS Logic BWR Submit report of feasibility 4/1 / 81 Modifications of ADS system logic changes to eliminate need for manual actuation.
- II. K. 3. 21 -
CSS /CPCI Restart BWR Submit report of evaluation, 1/1 /81 proposed modifications and analysis ( satisfy staff positions.
II.5 RCIC Suction SWR w/RCIC Implement procedures and 1/1 /81 document verification of this change.
II.K.3.27-Con =on Reference BWR Implement change end submit 1/1 / 51 for H O Level Instruments documentation of changes.
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-II.K.3.29
. Isolation SWR w/ICs Submit evaluation of I.C.
4/1/81 Condensor perfo r=ance.
l' performance i
II.K.3.30 SS LOCA Methods ALL Submit outline of program 11/15/80 for model.
II.K.3.a4.
Fuel Failure BWR Submit evaluation to verify 1/1/81 no fuel failure.
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.II.K.3.a5 Manual Depressur-BWR Submit evaluation on other 1 /1 / 51 ization than ADS method-for depressurization.
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Impl/ Doc Iten.
Title Applicability Specific Requirement Su,bm Due Dates 11I.0.3.3
' Improved Inplant ALL Have available means to 1/1/81 Iodine. Monitoring accurately measure airborne radioiodine inplant during an accident.
. *II.D.3.4-Control Room Habitability ALL a.
Submit control room 1/1/81 habitability evaluation in fo rmation, b.
Submit modifications 1/1/81 necessary to assure CR habitability with a schedule for completion.
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