ML20246C981
| ML20246C981 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Seabrook |
| Issue date: | 05/03/1989 |
| From: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Murley T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20246C819 | List: |
| References | |
| FOIA-89-226 IEB-88-010, IEB-88-011, NUDOCS 8908250210 | |
| Download: ML20246C981 (4) | |
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Ok UNITED' STATES is NUCLEAR REGULATORY COMMISSION -
O MEGION 1 s
475 ALLENDALE ROAD q
KING OF PRUSSIA PENNSYLVANIA 19406 MAY 031989 MEMORANDUM FOR: Thomas E. Murley, Director Office of Nuclear Reactor Regulation FROM:
William T. Russell, Regional Administrator Region I
SUBJECT:
SEABROOK STATION, UNIT 1 LOW POWER LICENSE RECOMMENDATION, SUPPLEMENT 1 This memorandum provides an update to my November 22, 1988, low power license recommendation.
This update reports the closure of the technical issue asso-ciated with Agastat 7000 series relays and provides the status of two NRC Bulletins issued since my initial recommendation.
It also discusses a recent series of events which have occurred.
Regarding the Agastat 7000 series relays, licensee action involved replacement of. five relays and is complete.
Regien I inspection of this activity has been satisfactorily completed and this issue is considered closed.
NRC Bulletin 88-10 concerning nonconforming molded case circuit breakers was issued on November 22, 1988.
Based upon licensee actions taken in response to NRC Information Notice 88-46 and the action plan developed by New Hampshire Yankee (NHY) to comply with Bulletin 88-10, Region I believes that this issue is being appropriately dispositioned by the licensee.
NRC Bulletin 88-11 concerning pressurizer surge line thermal stratification was issued on December 20, 1988.
An ongoing dialogue has occurred between NHY and NRR on the low power implications of this Bulletin. No additional inspection is needed on this Bulletin to support low power licensing.
Recently, several minor events ar.d problems have occurred at the site which raise NRC concern over the attention to detail in operations displayed by the plant staff.
The most significant of these involve two violations of the i
special zero-power license conditions associated with locked valves.
While l
none of the individual events or problems had an impact on safety, taken l
together they indicated a possible declining trend in facility performance.
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The licensee has taken corrective action for the individual instances and has developed and implemented an approach to improve attention to detail throughout the organization which involves observations and reviews through the self-assessment process.
Region I will monitor the effectiveness of these licensee activities through heatup and initial low power operations.
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Memorandum for Thomas E. Murley 2
Enclosures 1 and 3 of my November 22, 1988 memorandum are also updated for j
information.
In conclusion, I continue to find that Seabrook Unit I remains ready to conduct initial criticality and low power testing operations.
William T. Russell Regional Admir.istrator
Attachment:
Updated Enclosures 1 and 3 to Region I's November 22, 1988 Memorandum cc w/ attachment:
V. Stello, EDO J. Taylor, EDO i
B. Clayton, EDO J. Partlow, NRR S. Varga, NRR B. Boger, NRR R. Wessman, NRR V. Nerses, NRR W. Kane, RI S. Collins, RI M. Knapp, RI T. Martin, RI J. Wiggins, RI D. Haverkamp, RI L. Doerflein, RI D. Ruscitto, SRI - Seabrook i
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ENCLOSURE 1 Inspection Summary-
' Inspection Inspection Inspection" Number __.
Areas
. Hours 88-15 Routine. Inspection of 434 Operational Safety, Maintenance Security,-Radiation Protection, Licensee Self Assessment, 4
Reportable Events and Previous Inspection Findings.
88-16 Inspection Number Not Used 88-17, Routine Inspection of Operational 97 Safety, Reportable Even's, t
Maintenance, NRC Bulletins and Information Notices and Previous Inspection Findings.
89 Routine Inspection of Operational 130 Safety, Licensee Reports, Design Changes, Maintenance, Training and Previous Inspection Findings.
89-02 Routine Inspection of the 39 Emergency Preparedness Program and Previous Inspection Findings.
89-03 Routine Inspection of Operational-150 (Est)*
Safety, Maintenance, Reportable Events and Previous Inspection Findings 89-04 Routine Inspection of Electrical 64 (Est)*
Maintenance, Licensee Action on the Information. Netice on Raychem Splices, Licensee Program for Controlling Quality of Emergency Diesel Generator Fuel Oil and Previous Inspection Findings Report Not Yet Issued.
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ENCLOSURE 3 i
NRC Bulletin Summa _ry Bulletin No.
Subject Status 88-03 Inadequate Latch Engagement Closed - Relays Replaced-in HFA Type Latching Relays 10/88. Licensee response Manufactured by General 12/88. NRC inspection;1/89.
Electric (GE) Company.
88-04 Potential Safety-Related Open
-Licensee response Pump Loss.
8/88.
Licensee Engineering Evaluation. completed. Follow-up response 12/88.. Licensee response appears satisfac-tory.
No ' additional inspec-i tion needed to support licen-sing.
88-05 Nonconforming Materials Closed - Licensee responses Supplied by Piping Supplies, 8/88 and 10/88. Closecut SER Inc. at Folsom, New Jersey issued 12/88.
and West Jersey Manufacturing Company at Williamstown, New Jersey.
88-08 Thermal Stresses in Piping Open - Temporary modification Connected to Reactor Coolant installed to monitor for-Systems.
leakage.
Licensee responded 9/88.
Additional licensee response to NRR KAI 12/88.
No further inspection needed
'for licensing.
88-09 Thimble Tube Thinning.
Open Licensee inspection required at first refueling outage.
88-10' Nonconforming Molded Case Op$n Licensee action plan Circuit Breakers.
in place and response re-ceived 4/89.
Response ap-pears acceptable.
88-11 Pressurizer Surge Line Open - Licensee responses to Thermal Stratification conference call with NRR 12/88 describes action plan.
Westinghouse report submitted 3/89 and updated 4/89.
No further inspection needed for' licensing.
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