ML20118A649

Forwards 1992 Refueling Outage Summary of Completed Licensing Actions That Ended on 920816,covering NRC Bulletin 90-001,GL 88-17,plant Mods to Correct CR Heds & Reconsideration of ASME Code Repair of Pipe Flaw

ML20118A649
Person / Time
Site:	Calvert Cliffs
Issue date:	09/16/1992
From:	Creel G BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-88-17, IEB-90-001, IEB-90-1, TAC-M56110, TAC-M68525, TAC-M69730, TAC-M72075, TAC-M76537, TAC-M79911, TAC-M81522, TAC-M82363, NUDOCS 9209240295
Download: ML20118A649 (5)

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[ BAtTIMORC

[ l GAS AND

, ELECTRIC 1650 CALVERT CLIFFS PARKWAY e LUSBY, MARYLAND 20657 4702 O t.ono t C CnrtL.

st u>an vier P,a swa (410;000 3690 September 16,1992 U. S. Nuclear Regulatory Commission Washington, DC 20555 NITENTION: Document Control Desk SUll]ECT: Calvert Cliffs Nuclear Power Plant Unn No.1: Docket No. 50-317 1992 Refuehndjutace: Summary of Completed 1.icensint Actions N

Gentlemen:

Enclosure (1) summarizes various open licensing actions for Baltimore Gas and Electric Compar.y.

The actions were completed during the Refueling Outage that ended August 16,1992.

Should you have anv further questions regarding this matter. we will be pleased to discuss them with yoe.

% Very truly yours,

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,5 WW i for G. C. Creel Senior Vice President GCC/JMOldlm Enclosure cc: D. ^. Brune, Esquire f J. E. SJberg, Esquire [9TgC9 R. A. C.ipra, NRC gI D. G, MeDonald, Jr., N RC T. T. Martin, NRC -

P. R. Wilson, NRC R. L McLean, DNR /

/

J.11. Walter, PSC ;00 i

9209240293 920916 {

PDR ADOCK 05000317 P PDR

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e ENCLOSURE (1) 1992 ItEFUEl.ING OUTAGE SU5th1ARY l ,

SUlijECI': NRC Bulletin 90-01, Rosemount Transmitters (TAC No. h176537)

Iti.1'ERENCE: Letters from BG&E ta NRC, dated July 17,1930 and April 29,1992, same subject As lescribed in the referenced letters, all Unit 1 and Common Rosemount transmitters were repsaced by August 31,1992. Rephecment transmitters were manufactured after July 11,1989.

SUlljECr: NRC Generic Letter 8817, Loss of Decay IIca' Renrwal(TAC No. ht69730)

ItEFERENCE: Letter from BG&E to NRC, dated January 27,1989 and June 11,1991, same subject As described in the referenced letters, the following Unit 1 modifications were completed;

a. F cactor Coolant Sy:. tem wide- and narrow-range levelindicatkms and alarms;

b. Control Room Shutdown Cooling Flow indication Arm;

c. Control Room L w Pressure Safety Injection suction pressure indication; and

d. Core Exit Thermocouple audible alarm.

SUllJECT: Plant Modifications to Cotreet Control Room Iluman Engineering Deficiencies (IIED) (TAC No. h156110)

tEFERFNCE

L.etters from BG&E to NRC, dated July 6,1990 and June 30,19S3, same subject As described in the referenced letters, all Unit 1 IIED modifications have been completed witn the following exceptions:

FCR 88 208 hieters on plane B of Panels 17,18 and 20 will be rearranged.

The FCR wa:. cancelled for Units 1 and 2 as described in our letter dad hlarch 6,19(P These panel meters will be rearranged as part of installing two new Class iE emergency diesel generators.

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j?NCl,OSURE (11 1992 REFUELING OUTAGE

SUMMARY

FCR 88-210 Remount Control Room key lock switches that are not in the standard porition.

l The FCR was cancelled for Units 1 and 2 during an IIED Assessment Committec I meeting February 7,1992. . A- described in our letter dated lune 30,1988, if :l reassessment of a previously determined corrective action is deemed necessary, it l will be formally re evaluated to like standards used during the original assessment. l The committee concladed the modification was not necessary. The amount of time ,

it takes to turn the key over from teeth-up to teeth-down or vice versa, is nec,hgible J compared to the time required to retrieve the key from the key locker, l 1 i

FCR 88-218 Enhance Control Room lightmg. >

As described in our letter dated July 6,1990, the modification will be performed concurrently to both units. It will be completed prior to the restart of Unit 2 from -

the Spring 1993 Unit 2 Refueling Outage.

FCR 88-225 Add Auxiliary Feedwater (AITV) Pump suction pressure indication to Control Room Panel 1/2 C04.

The FCR was cancelled for Units 1 and 2 during IIED Assessment Committee meeting January 17,1992. The committee concluded that the modification was not necessary. The only available point to measure suction pressure is at the common-suction header. Consequently, operators would still be required to go to the AISV pc p room to evaluate AFW flow problems. There is a low suction pressure alarm in the Control Room. Secondary supporting indications use displayed in the -

Control Room . valve line-up, discharge pressure and Condensate Storage Tank level.

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SUlljECT: Reconsideration of ASME Code Repair of Pipe Flaw ' TAC No. MS1522)

ItEI'ERENCE: Letters from BG&E to NRC, dated April 25,1991, and September 6,1991, same subject As described in the referenced letteis, a Daw existed in a 6-inch veld-o-let _ inspection port to a 30 inch header down stream of the No.12 Saltwater / Service Wr.ter Heat Exchanger. The header was replaced with new p.pe.

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liNCLOSURE (1) 1992 REFUELING OUTAGE

SUMMARY

SUlijECI: Technical Specification Amendment to Isolation Valve Surveillance Requirement (TAC No. M82363)

ItEFERENCE: Letter from BG&E tt NRC, dated December 31,1991, same subject As described in the referenced letter, MOV444 was repaired during the recently completed Unit 1 outage. As we anticipated, only the valve stem was damaged. There was no damage to the valve seat or valve gate due to over. torquing.

SUllIECT: Increase in Auxiliary Feedwater (AFW) Actuation Delay T;me (TAC No. M72075)

REFERl'NCE: Letter from NRC to BG&E, dated December 4,1990. same subject As described in the referenced letter, Technical Specification Amendment 149 was issued to increase AFW actuation de!ay time from 54.5 seconda to 180 seconds. FCR 89 026, which ri,odifies the steam admission system including the time delay opening of contml valves, was comp!cted.

SUll. LECT: Station Blackout (SBO) Modification Status (TAC No. M68525)

ItEFERENCE: L.etter from BG&E to NRC, dated December 17,1991, same subject As described in the referenced letter, we have completed the SBO modifications associated with Unit 1. Specifically, we have provided DC. powered indicalit.n for some Unit 1 isolation valves and hase provided AC power (through the inverters) to the Reactor Vessel Level Monitoring System. ,

The remaining work can be perfonaed during power operation or will be performed during the Unit 2 refueling outage (ninth refueling outage). The schedule for completion of all SBO modifications (except the addition of emergency diesel generators) has not changed.

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, FSCI,OSilitE m 1992 REFtIEI,1NG OtJTAGE Silhlh1AltY l e i SUllJECT: Containtnent Pressure Instrument Tubing hiodification (TAC No. hl79911) 1(EFEltENCE: Letter from 13GkE to NRC, dated February 3,1992, same subject  !

We have completed the modifications required to bring the Unit 1 pressure instrument tubing into conformance with approved seismic analyses. As discussed in the referenced letter, we determined that the modification could not be dor,e safely during power operation and, therefore, took advantage of the < . fueling outage to complete the activity on Unit 1.

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