ML17055E675
| ML17055E675 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/21/1989 |
| From: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Burkhardt L NIAGARA MOHAWK POWER CORP. |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8905010014 | |
| Download: ML17055E675 (10) | |
Text
ACCE1Zl'ATED DlBUTJON DEMONSTRON SYFTEg REGULATORY INFORMATZON DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8905010014 DOC.DATE: 89/04/21 NOTARIZED: NO
'OCKET FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 AUTH.NAME AUTHOR AFFILIATION MARTIN,T.T.
Region 1, Ofc of the Director RECIP.NAME RECIPIENT AFFILIATION BURKHARDT,L.
Niagara Mohawk Power Corp.
SUBJECT:
Identifies remaining Reg Guide 1.97 activities for which NRC must agree w/util plans for resolution prior to restart.
DISTRIBUTION CODE:
IEOID COPIES RECEIVED:LTR 2 ENCL L SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:
RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: ACRS AEOD/DEIIB NRR SHANKMAN,S NRR/DLPQ/PEB 11 NRR/DOEA DIR 11 NRR/DREP/RPB 10 NRR/PMAS/ILRB12 OE ERMAN,J IL 02 EXTERNAL LPDR NSIC COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME SLOSSON,M AEOD DEDRO NRR/DEST DIR NRR/DLPQ/QAB 10 NRR/DREP/EPB 10 NRR/DRIS DIR 9A NUDOCS-ABSTRACT OGC/HDS 1 RGN1 FILE 01 NRC PDR COPIES LTTR ENCL 1
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Docket No.'50-220 Niagara Mohawk Power Corporation ATTN:
Mr. Lawrence Burkhardt, III Executive Vice President Nuclear Operations 301 Plainfield Road
- Syracuse, New York 13212 Gentlemen:
Subject:
Post Accident Monitoring Equipment (RG 1.97)
Restart Issues For Nine Mile Point Unit 1
The NRC has conducted two inspections at Nine Mile Point, Unit 1 to establish the status of your implementation of Regulatory Guide 1.97 (RG 1.97) issues and to determine the need for corrective actions.
The purpose of this letter is to identify those remaining RG 1.97 activities for which the NRC must agree with your plans and schedules for resolution prior to the restart of Unit l.
Following our first inspection, 88-34, conducted during the period November 14-18,
- 1988, two meetings were held with your staff to discuss unresolved RG 1.97 issues.
Your staff committed to correct related Equipment gualification and RG 1.97 equipment identification deficiencies prior to restarts A second inspection, 89-12, was subsequently conducted during the period March 27-31, 1989 to determine if further corrective actions were needed before restart.
This second inspection focused on the status of the most important RG 1.97 instruments (i.e. instruments important to the performance of Emergency Operating Procedures (EOPs) and those other instruments subject to Category 1
design criteria).
The inspection primarily addressed the redundancy
( single failure) separation and isolation deficiencies for this group of instruments and the availability of alternative methods of accomplishing safety functions should the specified monitoring instruments be unavailable.
As a result of inspection 89-12, we identified several significant deficiencies in Category 1 instruments (including the instruments that are important to the operators'mplementation of the EOPs).
Therefore, we request that you respond to this letter and specifically address the RG 1.97 related restart activities identified in Attachment A to this letter.
You should advise the NRC of your plans and schedules to address these issues as soon as possible and provide a
written response within 30 days of your receipt of this letter.
Your response should indicate an overall RG 1.97 action plan to cover the shor t term ( startup) and long term resolution of the RG 1.97 issues identified in Attachment A.
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APR 2 1
198S Niagara Mohawk Power Corporation Your cooperation with us in this matter is appreciated.
Sincerely, Thomas T. Martin, Director Division of Reactor Safety
Enclosure:
Attachment A, Nine Mile 1 RG 1.97 Restart Activities cc w/encl:
J.
A. Perry, Vice President, guality Assurance C.
- Mangan, Senior Vice President W. Hansen,
- Manager, Corporate guality Assurance C.
- Beckham, Manager, Nuclear equality Assurance Operations K. Dahlberg, Unit 1 Station Superintendent R. Randall, Unit 1 Superintendent, Operations J. Willis, General Station Superintendent C. Terry, Vice President Nuclear Engineering and Licensing J.
F. Warden, New York Consumer Protection Branch Troy B. Conner, Jr.,
Esquire John W. Keib, Esquire
- Director, Power Division, Department of Public Service, State of New York State of New York, Department of Law Licensing Project
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New York bcc w/encl:
Region I Docket Room (with concurrences)
DRP Section Chief Robert J.
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RI: IfRS Capra Anderson 4/ao/89 4/($ /89 I:DRS R)
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ATTACHMENT A NINE NILE POINT UNIT 1 RG 1. 97 RESTART ACTIVITIES 1.
Conduct an evaluation of RG 1.97 cable separation deficiencies.
a.
b.
C.
Identify potential cable separation deficiencies.
Evaluate the significance of the cable separation deficiencies.
Provide plans for necessary short and long term'esolution of the cable separation deficiencies'
~
Perform an evaluation of the RG 1.97 isolation deficiencies.
a.
Evaluate the significance of the isolation deficiencies on the availability of the important RG 1.97 monitoring instruments.
b.
Provide plans for necessary short and long term correction of the isolation deficiencies.
Perform a review of the RG 1.97 instrument circuit loading and the adequacy of installed fuses.
a.
Complete a
sample evaluation of two instrument circuits.
b.
Determine the need and provide a schedule for the further review of the other RG 1.97 instrument circuits.
4.
Review alternatives to the Category 1
RG 1.97 instruments for which deficiencies exist.
a.
Identify and document the usefulness of the alternatives to the RG 1.97 instruments for implementing the EOPs.
b.
Provide operator guidance and training as to when and how the alterna-tive instruments would be used.
5.
Complete the failure modes and effects analysis for the APRN isolation deficiencies.
a.
Complete the evaluation of this deficiency and take corrective actions.
b.
Provide the bases that no other protective functions are compromised by isolation deficiencies.
6.
Identify RG 1.97 instrument power sources.
Provide instrument power source information at the site in a form useful to the control room operators.
OFFICIAL RECORD COPY ANDERSON4/10/89 0003.0.0 04/21/89
Attachment A
Evaluate the safety significance of the Reactor. Pressure Vessel (RPV) common tap for the fuel zone water level instrument.
a.
Evaluate the safety significance of the common tap considering a
single passive failure at the common linc'etermine the operator's ability to follow the EOPs to assure adequate RPV water level and emergency coolant injection.
b.
Provide plans for resolution of this issue.
8.
Document and Docket Nine Mile 1
RG 1.97 restart activities.
b.
C.
Document the Niagara Mohawk (NM)
RG 1.97 evaluation of the parameters important to the EOPs that was performed to support NRC inspection 89-12.
Document the NM RG 1.97 Hazards Analyses.
Document planned RG 1.97 modifications.
Include scope and schedule.
Particular emphasis should be placed on modifications that address lack of redundancy for.important parameters (torus
- pressure, drywell atmosphere temperature, and drywell water level).
OFFICIAL RECORD COPY ANDERSON4/10/89-1 0003. 1. 0 04/21/89