ML20005F937
| ML20005F937 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/09/1990 |
| From: | Feigenbaum T PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-03, REF-GTECI-A-09, REF-GTECI-SG, REF-GTECI-SY, RTR-NUREG-0844, RTR-NUREG-844, TASK-A-03, TASK-A-09, TASK-A-3, TASK-A-9, TASK-OR GL-85-02, GL-85-2, GL-89-21, NYN-90008, NUDOCS 9001170413 | |
| Download: ML20005F937 (3) | |
Text
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Nkw Hampshire i
Ted C, Fi * : r-Senior Vice President and Chief Operating Officer
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NYN-90008 January 9, 1990 l
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United States Nuclear Regulatory Commission Washington, DC 20555
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Attention: Document Control Desk
References:
(a)
Facility Operating License.No. NPF-67. Docket No. 50-443 l
(b)
USNRC Generic Letter 89-21 dated October 19, 1989,
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' Request for Information Concerning Status of i
Implementation of Unresolved Safety Issue (USI)
Requirements' i
(c)
NHY Letter NYN-89162 dated December 11 1989, ' Response to Generic Letter 89-21,' T. C. Feigenbaum to USNRC i
f (d)
NHY Letter NYN-89084 dated July 6, 1989, 'ATWS Mitigation System ' T. C. Feigenbaum to USNRC' J
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Subject:
Supplemental Response to Generic Letter 89-21 j
Gentlemen:
This letter provides additional information regarding the status of' implementation at Seabrook Station of two Unresolved Safety Issues for p
which final technical resolution has been achieved.
The first Unresolved Safety Issue (USI) is USI No.-A-3 entitled j
' Westinghouse Steam Generator Tube Integrity.' In Reference (c), NHY
-l stated that this USI was incomplete pending verification of the completion i
status of commitments made in response to Generic Letter 85-02.
Generic i
Letter 85-02 delineated the NRC Staff recommended actions for an overall program for steam generator tube integrity identified in NUREG-0844 as part of the resolution of USI No. A-3.
The Seabrook Station Unit,1 response to Generic Letter 85-02 was contained in PSNH letter SBN-815, dated June 13, 1985.
New Hampshire Yankee has reviewed PSNH letter SBN-815 and verified that commitments made therein have been completed except as follows.
Two~ specific commitments associated with main condenser inspections-l have not been completed as of-this date. The two commitments are 1.
- Establish a prioritised surveillance list of condenser air i
in-leakage points to check.'
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2.
' Establish visual inspection criteria for water boxes and tube sheets.'
i 9001170413 900109 p
PDR ADOCK 05000443 P
PDC 3
New Hampshire Yonkee Division of Public Service Company of New Hampshire.
P.O. Box 300
- Seabrook, NH 03874
- Telephone (603) 474 9521
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United States Nuclear Regulatory Commission January 9, 1990 l
Attention Documet4t Control Desk Page 2 With regard to Commitment No. 1, approved NHY procedures provide a l
method to identify main condenser air inloakage.
These procedures list potential air inleakage points to checks but these points are not currently prioritised. NNY will review these procedures and revise them as necessary in light of Commitment No. 1. _In order to properly prioritiae potential air inleakage points, some operating time at power will be required. Therefore, NKY plans to review these procedures and revise them as necessary by August 31, 1990. With regard _to Commitment No. 2, periodic. inspections of the main i
condenser water. boxes and tube sheets have been conducted by an independent
-contractor in support of an existing warranty. Upon expiration of this warranty, the associated inspections will terminate and a replacement inspection program for water boxes and tube sheets will be implemented.
It is expected that the replacement inspection program will be formulated by December 31, 1990.
In summary, NHY has verified that commitments made in response to Generic Letter 85-02 have been completed or implemented in the following areast secondary side loose parts detection, steam generator tube inspection, secondary water chemistry, primary to secondary leakage limits and coolant iodine activity limits. Actions remain to be implemented in support of main condenser inspection programs.
These actions are planned and will be implemented at the appropriate time.
Thus, to the extent practical to date, NHY has completed actions associated with implementation of this USI.
The second Unresolved Safety Issue is USI No. A-9 entitled
' Anticipated Transients Without Scram (ATWS).' In Reference (c), NHY stated that this USI was incomplete pending installation of the ATWS Mitigation System. In Reference (d) NHY stated that installation of.the ATWS Mitigation System will be completed on or before August 31, 1990.. In Reference (d), NHY included the completion of testing within the meaning of
' installation'.
To date, the ATWS Hitigation System has been installed but not fully tested.
Instrumentation loop testing including the associated ATWS bistables and logic testing has been completed. An integrated ATWS Mitigation System test is scheduled to be completed by August 31, 1990. This integrated system test will verify that the ATWS Mitigation System initiates the Emergency Feedwater (EPW) System and trips the turbine. In an effort to complete ATWS Mitigation System testing as soon as possible, NHY will endeavor to complete the integrated system test prior to entry into Mode 1.
- Thus, implementation of.this USI at Seabrook Station will be completed on or before August 31, 1990.
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' $nited States Nuclear Regulatory Conunission January 9, 1990 Attention:
Document Control Desk Page 3 If you have any questions on this matter, please contact Mr. Geoffrey Kingston at (603) 474-9521 extension 3371.
Sincerely yours,
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MA-
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Ted C. Feigenbaum cci Mr. William T. Russell Regional Administrator United States Nuclear Regulatory Comunission Region 1 475 Allendale Road King of Prussia. PA 19406 Mr. Victor Nerses. Project Manager Project Directorate I-3 United States Nuclear Regulatory Commission Division of Reactor Projects Washington, DC 20555 NRC Senior Resident Inspector P.O. Box 1149 Seabrook, NH 03874 I
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