ML20081L894
| ML20081L894 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/27/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081L890 | List: |
| References | |
| NUDOCS 9503310071 | |
| Download: ML20081L894 (4) | |
Text
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J UNITED STATE'S L T
3 NUCLEAR REGULATORY COMMISSION k..... [i WASHINGTON, D.C. 20666-4001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENOMENT NO.162 TO FACILITY OPERATING LICENSE NO. DPR-35
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BOSTON EDISON CONPANY i
0 PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293
1.0 INTRODUCTION
4 By letter dated September 6,1994, the Boston Edison Company (the licensee) submitted a request for changes to the Technical Specifications -(TSs) for.the Pilgrim Nuclear Power Station (PNPS). 'The requested changes would reduce the high reactor pressure setpoint'for closure of the shutdown cooling isolation
'1 valves changed from s110 psig to $76 psig in TS Table 3.2.A, " Instrumentation that Initiates Primary Containment Isolation."' The low reactor pressure permissive for closure of the residual heat removal (RHR) low-pressure coolant injection (LPCI) valves is also changed from $110 psig to s76 psig in TS Table 3.2.B, " Instrumentation that Initiates or Controls the Core and Containment.
Cooling Systems." The bases for Section 3.2 have also been modified. The setpoint. changes are part of Generic Letter 89-10 program for PNPS.
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' From a systems viewpoint, the NRC staff is concerned with the impact of the changes on the performance of the LPCI and the shutdown cooling system modes
-of the RHR system.
l Description of Proposed Changes to Pilgrim Technical Specifications
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Page 45 -
Revise Table 3.2.A, " Instrumentation that Initiates Primary
-Containment Isolation," by changing the trip level setting for reactor high pressure from s110.psig to s76 psig.
Page 48 -
Revise Table 3.2.B, " Instrumentation that Initiates or_ Controls L
the Core and Containment Cooling Systems," by changing the trip L
level setting for reactor low pressure from $110 psig to s76 psig.
Page 68 -
Revise the TS bases, Section 3.2, by inserting the following paragraph:
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" Reactor pressure instrumentation is used for closure of Group 3 isolation valves and is set to trip at s76 psig. This prevents overpressurization of the RHR shutdown coolingpiping. The isolation setpoint is chosen:
(1) at a pressure below where the RHR piping could be overpressurized, (2) so that the isolation valves can close in the required time, and (3) at the point where the maximum differential pressure associated with the isolation valves is not exceeded."
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c 2.0 EVALUATION i
TS Table 3.2.A, " Instrumentation that Initiates Primary Containment Isolation," includes a reactor high-pressure setpoint at s110 psig to close the shutdown cooling isolation valves to provide overpressure protection for the RHR low-pressure suction piping. The shutdown cooling isolation valves (M0-1001-47,MD-1001-50) are located on the shutdown cooling line which is connected to the loop A recirculation pump suction. The amendment changes this setpoint to s76 psig. Shutdown cooling isolation.at a lower pressure is conservative because the margin to RHR system overpressurization increases.
Shutdown cooling is generally not required while system pressure is between 76.
and 110 psig, and the setpoint change does not affect LPCI operation.
Therefore, the change is acceptable.
TS Table 3.2.B, " Instrumentation that Initiates or Controls the Core and Containment Cooling Systems," includes a permissive at s110 psig for closure of the RHR LPCI inboard injection valves which is being changed to s76 psig to maintain consistency with the design of other group 3 valves that receive the high reactor pressure signal. The LPCI injection valves (MD-1001-29A,MO-1001-29B) are located outside the drywell on the RHR pump discharge lines leading:
to the recirculation pump discharge lines. The isolation of the RHR pump l
discharge lines does not effect LPCI initiation and does not prevent the LPCI injection valves from opening at pressures higher than 76 psig upon receipt of an injection signal. Therefore, the setpoint change will not affect normal LPCI operation. Shutdown cooling will also not be affected by the setpoint change, as shutdown cooling is generally not required while system pressure is between 76 and 110 psig. This change is acceptable.
The NRC staff has determined tN t the changes in isolation setpoints for the t
shutdown cooling isolation valve and the inboard RHR LPCI injection valves will not affect the performance of the shutdown cooling or LPCI modes of RHR, i
and are acceptable.
3.0 STATE CONSULTATION
i
.In accordance with the Commission's regulations, the Massachusetts State
. official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIR0feiENTAL CONSIDERATION I
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards
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. consideration, and there has been no public comment on such finding (59 FR 53837). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
G. Golub Date: March 27, 1995
6 March 27, 1995 DISTRIBUTION:
OGC --15818 Docket File GHil1~(2) T-5C3 PUBLIC CGrimes - 11E22
'Mr. E. Thomas Boulette, Ph.D PDI-I Reading ACRS I4)
Senior Vice President - Nuclear SVarga OPA - 2G5 Boston Edison Company JZwolinski OC/LFDCB Pilgrim Nuclear Power. Station LMarsh'
-JLinville, RI RFD #1 Rocky Hill Road Slittle JWermiel l
Plymouth, MA 02360 REaton KCotton GGolub
SUBJECT:
ISSUANCE OF AMEN 0 MENT NO.162 TO FACILITY OPERATING LICENSE NO.
i DPR-35, PILGRIM NUCLEAR POWER STATION (TAC NO. M90367) i
Dear Mr. Boulette:
The Commission has issued the enclosed Amendment No. 162 to Facility i
Operating License No. DPR-35 for the Pilgrim Nuclear Power Station. This amendment is in response to your application dated September 6,-1994.
This amendment would reduce the reactor pressure setpoint at which the shutdown cooling system automatically isolates. This setpoint also isolates the low pressure coolant injection valves when the shutdown cooling system.is in operation.
A copy of the related Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Reaister Notice.
Sincerely, Original signed by:
l Ronald B. Eaton, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II
'r Office of Nuclear Reactor Regulation Docket No. 50-293
Enclosures:
1.
Amendment No.162 to License No. DPR-35 2.
Safety Evaluation cc w/encls:
See next page DOCUMENT NAME: A:\\PI90367.AMD s, *u.
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