ML20045H650

Provides Summary of Various Open Licensing Actions for Plant.Actions Contained in Encl 1 Completed During Refueling Outage Ended 930611

ML20045H650
Person / Time
Site:	Calvert Cliffs
Issue date:	07/12/1993
From:	Denton R BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9307210088
Download: ML20045H650 (6)

Text

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BALTIMORE -

GAS AND ELECTRIC i

1650 CALVERT CLIFFS PARKWAY. LUSBY, MARYLAND 20657-4702 ROBERT E. DENTON Vict PRESIDENT NuctE AR ENERGY (4 o) 360 4a55 July 12,199 U. S. Nuclear Regulatory Commission Washington, DC 20555 NITENTION:

Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No.1 & 2; Docket Nos. 50-317 & 50-318 1993 Refueline Outate: Summary of Completed Licensine Actions

REFERENCE:

(a)

Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated September 16,1992, "1992 Refueling Outage; Summary of Completed Licensing Actions" Enclosure (1) summarizes various open licensing actions for Baltimore Gas and Electric Company (BG&E).

Additionally, it provides more information to justify cancellation of two Human Engineering Deficiency plant modifications. A follow-on telephone discussion between NRC and BG&E staff regarding Reference (a) requested these additional details.

The actions contained in Enclosure (1) were completed during the Refueling Outage that ended June 11,1993.

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

Very truly yours, 7

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1. for R. E. Denton Vice President -Nuclear Energy RED /JMO/jmo/dtm

- Enclosure

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- Document Control Desk July 12,1993 Page 2 -

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D. A. Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC D. G. Mcdonald, Jr., NRC i

T. T. Martin, NRC i

P. R. Wilson, NRC R.1. McLean, DNR J. II. Walter, PSC 1

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ENCLOSURE m i

1993 REFUELING OUTAGE

SUMMARY

SUllJECT:

NRC Bulletin 90-01 and its Supplement 1. Rosemount Transmitters (TAC Nos. M76538 & Mfs5370)

REFERENCE:

Letters from BG&E to NRC, dated July 17,1990, and March 4,1993, same subject As committed to in the referenced letters, all Unit 2 Rosemount transmitters were replaced by.

May 12,1993. Replacement transmitters were manufactured after July 11,1989. All actions for this item are complete for Units 1 and 2.

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SUllJECT:

NRC Generic Letter 88-17, Loss of Decay Heat Removal (TAC No. M69731)

REFERENCE:

Ixtter from BG&E to NRC, dated January 27,1989 June 11,1991 and June 7,1993, same subject As committed to in the referenced letters, the following Unit 2 modifications were completed:

. Reactor Coolant System (RCS) wide-range level indications and alarms; a.

b.

Control Room Shutdown Cooling Flow indication alarm; c.

Control Room Low Pressure Safety Injection suction pressure indication; and d.

Core Exit Thermocouple audible alarm.

As described in our June 7,1993 letter, the narrow-range RCS level was installed. However, due to circuit noise problems that developed during acceptance testing, the acceptance test could not be completed without severely impacting the refueling outage length. With this one exception, all actions for Generic Letter 88-17 are complete for Unit 2. All Unit 1 actions were reported complete in our letter dated September 16,1992.

SUllJECT:

Plant Modifications to Correct Control Room Human Engineering Deficiencies (HED)(TAC Nos.M56110 & M56111)

REFERENCE:

Letters from BG&E to NRC, dated July 6,1990 and June 30,1988, same subject As committed to in the referenced letters, all Unit 1 & 2 HED modifications have been completed.

As committed to in our letter dated July 6,1990, the Enhanced Control Room lighting modification was completed concurrently for Units 1 & 2. Three other HED modifications were reevaluated during the spring 1992 refueling outage and cancelled. They are described below:

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I ENCLOSURE m 1993 REFUELING OUTAGE

SUMMARY

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

The FCR was cancelled for Units 1 and 2 as described in our letter dated March 6,1992. These panel meters will be rearranged as part ofinstalling two new Class 1E emergency diesel generators.

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

The FCR was cancelled for Units 1 and 2 during an HED Assessment Committee meeting February 7,1992. As described in our letter dated June 30,1988, if reassessment of a previously determined corrective action is deemed necessary, it will be formally re-evaluated to like standards used during the riginal assessment.

The committee concluded the modification was not necessary for the following reasons:

(1) The amount of time it takes to turn the key over from teeth-up to teeth-down or vice versa, is negligible compared to the time required to retrieve the key from the key locker.

(2) Every key was tested in the plant simulator to determine if it could be partially inserted, jammed and/or potentially broken off in the key lock.

Based on the design of the keyhole, an " upside down" key cannot be inserted to any appreciable degree that could lead to jamming the key. Therefore, the orientation of the key lock could not by itself cause a plant function to be lost.

(3) Numerous keys are left in the key locks and selected to their normal position.

(4) After the key is inserted, it is under operator control and its orientation relative to teeth-up versus teeth-down is not a safety significant issue.

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

8 The FCR was cancelled for Units 1 and 2 during HED Assessment Committee meeting January 17,1992. The committee concluded that the modification was not necessary. The original reason for the modification was an incorrect perception by operators that frequent AFW pump maintenance had been required in the mid-1980s time frame. A maintenance history review determined it was improper maintenance to the pump motor, not the pump, that had led to a series of failures.

Therefore, the modification was not justified based on pump failures. Similarly, when the existing group of indications and alarms associated with AFW were reviewed, there was little justification for adding the AFW suction pressure indication. Other key points from the assessment committee's review follow:

1 (1) A low suction pressure condition will actuate an alarm in the Control Room.

(2) Sceandary supporting indications are displayed in the Control Room - valve line-up, pump motor amp indication and Condensate Storage Tank levels.

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ENCLOSURE (1) 1993 REFUELING OUTAGE

SUMMARY

(3) Suction valves to the AFW pumps are administratively locked open.

(4) The AFW pumps have local indication of suction pressure.

(5) Auxiliary feedwater flow and discharge pressure indication are available in the Control Room.

(6) The only available point to measure suction pressure is at the common suction header. Consequently, even if the modification was added, operators would still be required to go to the AFW pump room to evaluate and correct the specific AFW pump suction flow problem.

SUllJECT:

Station Blackout (SBO) Modification Status (TAC No. M68526)

REFERENCE:

Letter from BG&E to NRC, dated December 17,1991, same subject All of the SBO modifications committed to in the referenced letter have now been completed.

Specifically, we have provided DC-powered position indication for the appropriate Unit 2 isolation valves and have provided AC power (through the inverters) to the Unit 2 Reactor Vessel Level Monitoring System. We have also completed modifications to the Control Room drop ceiling and added temperature monitors to the battery rooms. This completes all of our SBO modifications for Units 1 and 2 except those associated with the addition of the diesel generators.

SUllJECT:

C(mtainment Pressure Instrument Tubing Modification (TAC No. M79912)

REFERENCE:

Letter from BG&E to NRC, dated February 3,1992, same suSject We have completed the modifications required to bring the Unit 2 pressure instrument tubing into conformance with the damping values described in the UFSAR. As discussed in the referenced letter, we determined that the modification could not be done safely during power operation. All action for this item is complete for Units 1 and 2.

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' ENCLOSURE (1) 1993 REFUELING OUTAGE

SUMMARY

SUllJECT:

Weld Repair to Unit 2 Refueling Water Tank (RWT) (TAC No. M82749)

REFERENCE:

Letter from BG&E to NRC, dated February 11,1992, " Request for Temporary Relief from ASME Boiler and Pressure Vessel Code Section XI Requirement IWA-5250" We have completed repair of the weld to the Unit 2 RWT that we committed to in the referenced letter. All action for this item is coraplete.

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