ML20126E668
| ML20126E668 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/15/1992 |
| From: | Eaton R Office of Nuclear Reactor Regulation |
| To: | Richard Anderson BOSTON EDISON CO. |
| References | |
| TAC-M85069, NUDOCS 9212290259 | |
| Download: ML20126E668 (6) | |
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December 15, 1992 Docket No. 50-293 Mr. Roy A. Anderson Senior Vice President - Nuclear Boston Edison Company Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360
Dear Mr. Anderson:
SUBJECT:
PILGRIM NUCLEAR POWER STATION, INSERVICE TEST PROGRAM FOR THIRD 10-YEAR INTERVAL (TAC NO. M85069)
Boston Edison Company submitted the updated inservice testing program for the Pilgrim Nuclear Power Station in their letter dated November 25, 1992, in accordance with 10 CFR 50.55a. The third ten-year inservice testing interval began December 10, 1992. The licensee has scheduled refueling outage (RF0)
- 9 for April 1993 and has requested interim staff approval of the inservice testing prbgram relief requests until the staff review and evaluation is complete.
Particularly, the following items were listed for a " priority" review:
Cold Shutdown Justification CSJ 17 - The staff does not evaluate cold shutdown justifications in Safety Evaluations.
However, deferring testing of main steam isolation valves full-stroke exercising from power operations to cold shutdown appears to be justified.
This item will be subject to NRC inspection.
Relief Request RV High pressure coolant injection system exhaust drain pot isolation solenoid operated valves cannot currently be stroke-timed. NRC previously granted interim relief until the third ten-year interval. A modification scheduled for RF0f9 (April 1993) will replace these valves with valves that can be tested in accordance with the Code requirements, it is acceptable to the staff to begin stroke-time testing of these valves subsequent to replacement.
The Safety Evaluation will consider that the replacement is to be complete prior to startup from the April 1993 refueling outage.
Relief Request RV This request is to allow closure verification of various check valves to be performed every two years by leakage testing. The staff will review each specific case and may require more frequent testing, depending on the impracticality of performing leakage testing during power operations or cold shutdown conditions.
The licensee should ensure that all of the applicable valves are leakage tested during the April 1993 refueling outage for the interim until the staff issues the Safety Evaluation.
Relief Request RV Pump discharge check valves will be tested on a frequency established for full-flow testing of the respective pumps in the 7212290259 921215
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reactor building closed cooling water and salt seri exceed a refueling interval frequency.
The licensa valves are tested during the April 1993 refueling (
the staff issues the Safety Evaluation.
Relief Request RV The licensee proposes to follow ti.,
Technical Specifications for mode changes. When valves testeu i
shutdown frequency f all to meet the acce)tance criteria, plant st,
proceed if the valve is not required to )e operable.
The staff finds t..
acceptable on an interim basis for valves in systems included in Technical Specifications.
For the remaining valves, a determination that the affected system operability is not required for mode changes must be performed for each particular valve.
This will be further addressed in the staff's Safety Evaluation.
Relief Request RV The licensee proposes to test the main steam isolation and safety relief valve pilot assemblies using a slave main valve body.
The proposal is acceptable for any testing performed prior to receipt of the staff's Safety Evaluation provided the licensee ensures that adequate quality controls exist for reinstallation of the pilot assemblies following testing.
This will be further discussed in the staff's Safety Evaluation.
Relief Request RV For the residual heat removal system check valves 68A/B, the testing will be staggered on a cold shutdown testing frequency, not to exceed testing both valves on at least a refueling outage basis.
The testing of both valves on a cold shutdown frequency requires operation of both loops and swapping the shutdown cooling function.
This creates a " higher risk evolution" and a potential loss of shutdown cooling.
The proposal is acceptable until the staff performs a detailed evaluation of this request.
The remaining relief requests appear to be consistent with the previous 10-year interval program, or have been revised to address concerns identified in NRC Safety Evaluation, Revision 1, dated February 3,1992. The staff projects that the Safety Evaluation for the third 10-year interval will be issued by June 1, 1993. The new program should be implemented in the interim period in accordance with the revised requirements.
Sincerely, Ronald B. Eaton, Senior Project Manager Project Directorate 1-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:
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Hr. Roy A. Anderson December 15, 1992 reactor building closed cooling water and salt service water system, not to exceed a refueling interval frequency.
The licensee should ensure that these valves are tested during the April 1993 refueling outage for the interim until the staff issues the Safety Evaluation.
Relief Request RV The licensee proposes to follow the recuirements of Technical Specifications for mode changes. When valves testec on a cold shutdown frequency fail to meet the acce)tance criteria, plant startup will proceed if the valve is not required to >e operable. The staff finds this acceptable on an interim basis for valves in systems included in Technical Specifications.
For the remaining valves, a determination that the affected system operability is not required for mode changes must be performed for each particular valve.
This will be further addressed in the staff's Safety Evaluation.
Relief Request RV The licensee proposes to test the main steam isolation and safety relief valve pilot assemblies using a slave main valve body. The proposal is acct.ptable for any testing performed prior to receipt of the staff's Safety Evaluation provided the licensee ensures that adequate quality controls exist for reinstallation of the pilot assemblies following testing.
This will be further discussed in the staff's Safety Evaluation.
Relief Request RV For the residual heat removal system check valves 68A/B, the testil will be staggered on a cold shutdown testing frequency, not to exceed testing oth valves on at least a refueling outage basis.
The testing of both valves on a cold shutdown frequency requires operation of both loops and swapping the shutdown cooling function. This creates a " higher risk evolution" and a potential loss of shutdown cooling. The proposal is acceptable until the staff performs a detailed evaluation of this request.
The remaining relief requests appear to be consistent with the previous 10-year interva' program, or have been revited to address concerns identified in NRC Safety Evaluation, Revision 1, dated February 3, 1992.
The staff projects that the Safety Evaluation for the third 10-year interval will be issued by June 1, 1993.
The new program should be implemented in the interim period in accordance with the revised requirements.
Sincerely, l
]V onald B. Eaton, Senior Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:
See next page i
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a 0-Mr. R. A. Anderson Pilgrim Nuclear Power Station l
cc:
i Mr. E. Thomas Boulette, Mr. H. Vernon 0heim.
Vice President of Nuclear Manager, Reg. Affairs Dept.
Operations & Station Director Pilgrim Nuclear Power Station l
Pilgrim Nuclear Power Station RFD #1 Rocky Hill Road l
RFD #1 Rocky Hill Road Plymouth, Massachusetts 02360 t
Plymouth, Massachusetts 02360 Mr. David Terantino Resident inspector Nuclear Information-Manager a
U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Pilgrim Nuclear Power Station RfD #1, Rocky 11111 Road Post Office Box 867 Plymouth, Massachusetts 02360 Plymouth, Massachusetts 02360 Mr. Thomas Ra)one Chairman, Board of Selectmen Secretary of )ublic Safety 11 Lincoln Street Exacutive Office of-Public Safety Plymouth, Massachusetts 02360 One Ashburton Place Boston, Massachusetts 02108 Office of the Commissioner Massachusetts Department of Mr. David Rodham, Director Environmental Protection Massachusetts-Emergency Management One Winter Street Agency Boston, Massachusetts 02108 400 Worcester Road P.O. Box 1496 Office of the Attorney General Framingham, Massachusetts 01701-0317 One Ashburton Place Attn: James Muckerheide 20th Floor Boston, Massachusetts 02108 Chairmen, Citizens Urging Responsible Energy Mr. Robert M. Hallisey, Director P. O. Box 28i21 Radiation Control Program Duxbury, Massachusetts 02331 Massachusetts Department of Public Health Citizens at Risk 305 South Street P. O. Box 3803 Boston, Massachusetts 02130 Plymouth, Massachusetts 02361 Regional Administrator, Region 1 W
S. Stowe, Esquire U. S. Nuclear Regulatory Commission Boston Edison Company 475 Allendale Road 800 Boylston St.,-36th Floor-King of Prussia, Pennsylvania 19406 Boston, Massachusetts 02199 Mr. Paul _G. Hamilton Licensing-Division Manager Boston Edison Company 25 Braintree Hill-Park Braintree, Massachusetts 02184 m
I Mr. Roy A. Anderson,
december 15, 1992 reactor building closed cooling water and salt service water system, not to exceed a refueling interval frequency.
The licensee should ensure that these valves are tested during the April 1993 refueling outage for the interim until the staff issues the Safety Evaluation.
Relief Request RV The licensee proposes to follow the recuirements of Technical Specifications for mode changes. When valves testec on a. cold shutdown frequency fall to meet the accestance criteria, plant startup will proceed if the valve is not required to ae operable.
The staff finds this acceptable on an interim basis for valves in systems included in Technical
/
Specifications.
For the remaining vahes, a determination that the affected system operability is not required for mode changes must be performed for each particular valve.
This will be further addressed in the staff's Safety Evaluation.
Relief Request RV The licensee proposes to test the main steam isolation and safety relief valve pilot assemblies using a slave main valve body.
The proposal is acceptable for any testing performed prior to receipt of the staff's Safety Evaluation provided the licensee ensures that adequate quality controls exist for reinsta11ation of the pilot assemblies following testing.
This will be further discussed in the staff's Safety Evaluation.
Relief Request RV For the residual heat removal system check valves 68A/B, the testing will be staggered on a cold shutdown testing frequency, not to exceed testing both valves on at least a refueling outage oasis. The testing of both valves on a cold shutdown frequency requires operation of both loops and swapping the shutdown cooling function. This creates a " higher risk evolution" and a potential loss of shutdown cooling.
The proposal is acceptable until the staff performs a detailed evaluation of this request.
The remaining relief requests appear to be consistent with the previous 10-year interval program, or have been revised to address concerns identified in NRC Safety Evaluation, Revision 1, dated February 3, 1992. The staff projects that the Safety Evaluation for the third 10-year interval will be issued by June 1, 1993. The new program should be implemented in the interim period in accordance with the revised requirements.
Sincerely, Ronald B. Eaton, Senior Project Manager Project Directorate I-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation cc:
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