ML19325D773
| ML19325D773 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 10/18/1989 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | Bird R BOSTON EDISON CO. |
| References | |
| NUDOCS 8910260129 | |
| Download: ML19325D773 (3) | |
Text
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't',i UNITED STATES
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NUCLEAR REGULATORY COMMISSION a
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WASHING TON, D. C. 20665
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October 18, 1989
....e Docket No. 50-293 Mr. Ralph G. Bird Senior Vice President - Nuclear Boston Edison Company Pilgrim Nuclear Power Station
, RFD #1 Rocky Hill Road Plymouth, Massachusetts 02360
Dear Mr. Bird:
l
SUBJECT:
RELIEF REQUEST RV-29 FROM ASME CODE INSERVICE TESTING REQUIREMENTS FOR TWO RESIDUAL HEAT REMOVAL SYSTEM YALVES - PILGRIM NUCLEAR POWER STATION
REFERENCE:
TAC NO 75032 (BEco) requested By letter dated September 22, 1989, relief from the American Society of Mechanical MineersBostonEdisonCompany(ASME)
XI, Sub-section 1WV 3422, which requires that it. <rvice testing (IST) be conducted at least every two years on specific valves. Your request, relief request RV-29, requested a one-time extension of the required testing to refueling outage number eight (RFO-8) and that the test frequency be changed from every two years to each refueling outage for Residual Heat Removal (RHR) system valves number MO-100-63 and CK-1001-64 The valves are normally closed and provide reactor coolant pressure isolation.
Yalve MO-1001-53 also performs a containment isolation function. Pressure isolation leak rate testing of the valves require removal of Class I head spray
' piping to allow installation of a blank flange.
Installation of this flange is typically performed in conjunction with removal of the drywell head and opening of the reactor pressure vessel, which is normally done only during refueling outages.
Performance of the tests prior to a refueling outage would be in a high radiation area and result in additional radiation exposure to the workers
> performing the required tests.
The. valves were successfully tested on October 31, 1987 and currently are required to be tested by October 31, 1989. The requested relief would grant a one-time extension of the tests to RFO-8 which is currently planned for March of 1991. You have indicated that the requested extendos will not result in a reduction of the margin of safety. The valves are de-c.nergized in the normally closed position and the Class I head spray piping is Aysically isolated from the RHR system by a welded cap. This configuration, which has existed since the last test, will not be altered until RFO-8 if the relief is granted.
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qr-v=w Mr. Ralph G. Bird October 18, 1989 i
You have indicated that normal refueling cycles at Pilgrim are less than two years. When cycles exceed two years, which is currently the case, testing will exceed the code requirement.
However, testing during RFOs should result i
overall in more frequent testing during the licensed life of the plant.
1 i
However, the staff has detemined that the request to change from every two years to each refueling outage to be unacceptable. The granting of a one-time i
extension to RFO-8, for the reasons previously discussed, should allow the valves to be tested within the code required two years in conjunction with future RFOs.
Therefore, in accordance with the requirements of 10 CFR 50.55(a)g, we have i
determined that the current requirement for testing valves MO-100-63 and CK-1001-64 prior to RF0-8 is impractical. This detemination is based on the l
achievable (ALARA consideration)g radiation exposure as low as roasonable system configuration, maintainin and the previous test results.
Thus, the portion of relief request RV-29 which requested an extension from testing prior to October 31, 1989 to RFO-8 is granted. We have also detemined, pursuant to 10 CFR 50.55(g)(6)(i), tha+ the granting of relief is authorized by law, will not endanger life or property or the comon defense and security and is otherwise in the public interest.
In making this determination, the staff has given due i
consideration to the burden that could result if the requirements were imposed on your facility.
This completes our action related to the referenced TAC number.
Sincerely, i
l Drlginalsigned by:
1 Richard H. Wessman, Director Project Directorate I-3 l
Division of Reactors Projects I/II Office of Nuclear Reactor Regulation cc:
See next page l
DISTRIBUTION fac4etJHt NPC PDR
'Jocal PDR PD1-3 Reading SVarga BBoger MRushbrook l
OGC (f/ info only)
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BGrimes ACRS(10) l JWiggins, RI l
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1 M shbrook DMcDonald:rw TMarsh RWessman g/89 10/10/89 10/11/89 j a/W89 go/gy/89 0F ICIAL RECORD COPY Document Name: TAC NO. 75032 PNPS
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'Mr. Ralph G. Bird CC' i
Mr. K. L. Highfill Mr. Richard N. Swanson, Manager Vice President of Operations /
Nuclear Engineering Departnent Station Station Boston Edison Company i
Pilgrim Nuclear Power Station 25 Braintree Hill Park RFD #1 Rocky Hill Road Braintree, Massachusetts 02184 Plymouth, Massachusetts 02360 Resident Inspector Ms. Elaine D. Robinson r
U. S. Nuclear Regulatory Commission Nuclear Information Manager Pilgrim Nuclear Power Station Pilgrim Nuclear Power Station i
Post Office Box 867 RFD #1, Rocky Hill Road Plymouth, Massachusetts 02360 Plymouth, Massachusetts 02360 Chairman, Board of Selectmen Mr. Charles V. Barry 11 Lincoln Street Secretary of Public Safety Plymouth, Massachusetts 02360 Executive Office of Public Safety One Ashburton Place Office of the Commissioner Boston, Massachusetts 02108 Massachusetts Department of Environmental Quality Engineering One Winter Street Boston, Massachusetts 02108 Office of the Attorney General One Ashburton Place 20th Floor Boston, Massachusetts 02108 Mr. Robert M. Hallisey, Director Radiation Control Program Massachusetts Department of Public Health 150 Tremont Street, 2nd Floor Boston, Massachuset.ts 02111 Regional Administrator, Region I i
U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. John Dietrich Licensing Division Manager i
Boston Edison Company 25 Braintree Hill Park Braintree, Massachusetts 02184
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