ML18022A999

Supplements Utils 970120 Ltr Re Violations Noted in Insp Rept 50-400/96-10.Corrective Actions: a ESW Pump Will Be Replaced During Refueling Outage 7 & Procedure AP-107, TS Interpretations, Has Been Revised to Clarify Purpose

ML18022A999
Person / Time
Site:	Harris
Issue date:	02/13/1997
From:	Robinson W CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
HNP-97-027, HNP-97-27, NUDOCS 9702130018
Download: ML18022A999 (4)

Text

CAj&GURY 1 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

.." ACCESSION.NBR:9702130018 DOC.DATE: 97/02/13 NOTARIZED: NO DOCKET C1'L:50-400 Hnearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 UTH.NAME AUTHOR AFFILIATION BINSON,W.R., Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION g[~jD Document Control Branch (Document Control Desk)

SUBJECT:

Supplements utils 970120 ltr re violations noted in insp rept 50-400/96-10.Corrective actions: "A" ESW pump will be replaced during Refueling Outage 7 & Procedure AP-107, "TS Interpretations," has been revised to clarify purpose.

DISTRIBUTION CODE: IE01D COPIES RECEIVED:LTR t ENCL 0 SIZE:

TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:Application for permit renewal filed. 05000400 G

RECIPIENT COPIES RECIPIENT COPIES

'ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD LE,N INTERNAL: ACRS AEOD/SPD/RAB AEOD T C DEDRO CEN NRR/DISP/PIPB R D CH/HHFB NRR/DRPM/PECB NRR/DRPM/PERB NUDOCS-ABSTRACT OE DIR OGC/HDS2 RGN2 FILE 01 D

E ERNAL: LITCO BRYCEiJ H NOAC NRC PDR 0 U

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESKr ROOM OWFN SD-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 19 ENCL

Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nucleal'lant SERIAL: HNP-97-027 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENT TO A REPLY TO NOTICE OF VIOLATION (NRC INSPECTION REPORT NO. 50-400/96-10)

Dear Sir or Madam:

On January 20, 1997, Carolina Power & Light Company (CP&L) submitted a reply to the Notice of Violation (NOV) enclosed in your Inspection Report 50-400/96-10 dated December 20, 1996.

The purpose of this letter is to supplement our previous reply regarding Reported Violation A "Failure to Promptly Submit a Technical Specification Change. for Main Reservoir Level." After further evaluation, an additional instance has been identified where'an existing Technical SpecificationInterpretation(TSI) implements a more conservative LimitingCondition of Operation than the Technical Specification.

TSI 95-003, Revision 3 "Ultimate Heat Sink" contained three administrative limits; (1) the main reservoir level shall be maintained at or above 215 feet mean sea level, (2) the temperature of both the Auxiliaryand Main reservoir shall be less than or equal to 94'F and, (3) at least one Emergency Service Water (ESW) pump shall be in operation ifeither reservoir's temperature is above 86'F.

As stated in our reply to the NOV, a proposed amendment to Technical Specification 3/4.7.5, "Ultimate Heat Sink," was submitted to the NRC on October 31, 1996 which reduces the maximum allowable water temperature from 95'F to 94'F and increases the minimum main reservoir level from 205.7 feet to 215 feet. The administrative limit requiring at least one ESW pump to be operating if either reservoir's temperature is above 86'F was not addressed in the proposed amendment. The running of one ESW pump eliminates the cross tie that would create reduced flow in the "A"train ESW header in the event of a single active failure.

CP&L plans to replace the "A" ESW pump during Refueling Outage No. 7. The new pump is exp'ected to return the system to a level ofperformance which willnegate the need for this restrictive condition. Ifthis modification is not successful in correcting the condition, an Operating License Amendment request will be submitted to the NRC, within 60 days of outage completion, to incorporate 'the requirement to have at least one ESW pump operating if either reservoir's temperature is above 86'F.

9702l300l8 9702l3 PDR ADOCK 05000400 8 PDR State Road 1134 New Hill NC Tel 919362-2502 Fax 919362-2095

0' Document Control Desk Serial: HNP-97-027/ Page 2 CP&L's reply to the NOV stated that Procedure AP-107, "Technical Specification Interpretations,"

had been revised to clarify the purpose and limitations of TSIs. The revised procedure allows TSIs to be used to impose more conservative limiting conditions of operations as interim measures to prevent operating the plant in a condition that is outside design basis. However, ifthe current LCO is determined not to meet the requirements of 10 CFR 50.36, the procedure required that a license amendment be prepared and submitted to the NRC within 60 days. This procedure has now been revised to allow the Vice President, Harris Nuclear Plant to permit exceptions to the 60 day submittal requirement.

Based on this supplement, full compliance with Appendix B Criterion XVI with regard to LCOs or proposed LCOs meeting the requirements of 10 CFR 50.36 will be achieved with the submittal of the proposed amendment to Technical Specification 3I4.7.1 (expected by February 28, 1997) and resolution of the ESW pump performance issue expected by the end of Refueling Outage No. 7.

Questions regarding this matter may be referred to Ms. D. B. Alexander at (919) 362-3190.

Sincerely, MGW Attachment Mr. J. B. Brady (NRC Resident Inspector, HNP)

Mr. N. B. Le (NRR Project Manager, HNP)

Mr. L. A. Reyes (NRC Regional Administrator, Region II)