ML20125E318

Discusses Summary of Licensing Actions Implemented During Refueling Outage Which Ended on 920816

ML20125E318
Person / Time
Site:	Calvert Cliffs
Issue date:	12/08/1992
From:	Mcdonald D Office of Nuclear Reactor Regulation
To:	Denton R BALTIMORE GAS & ELECTRIC CO.
References
TAC-M69730, TAC-M79911, TAC-M81522, TAC-M82363, NUDOCS 9212160298
Download: ML20125E318 (5)

Text

_

, . _. . -. d Q LEO

/ 'o

~g UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION

;;  ; WASWNGTON, D. C. 20555

\ ..... / December 8, 1992 Docket Nos. 50-317 4

and 50-318 Mr. Robert E. Denton Vice President - Nuclear Energy Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-4702 l

SUMMARY

OF LICENSING ACTIONS COMPLETED DURING THE 1992 REFUELING OUTAGE AND IMPLEMENTATION OF ACTIONS ASSOCIATED WITH TAC NOS. M69730, M81522, M82363, M79911, CALVERT CLIFFS NUCLEAR POWER PLANT, UtIT NOS. 1 AND 2 By letter dated September 16, 1992, Baltimore Gas and Electric Company (BG&E) provided to the NRC staff a summary of the licensing actions implemented during the refueling outage which ended on August 16, 1992. A total of eight issues were discussed in this letter. The first' issue, NRC Bulletin 90-01, Rosen.ount Transmitters, will be addressed in a separate letter.- A supplement to the Bulletin will be issued shortly. The remaining seven issues are-u aussed below.

l Generic letter 88-17. Calvert Cliffs Unit-1 (TAC No. M69730)' l l Generic Letter (GL) 88-17, Loss of Decay Heat Removal, requested programmatic enhancements which included nonhardware changes and hardware modifications.

By letter dated May 28, 1991, the NRC staff confirmed that nonhardware changes had been implemented for Units 1 and 2 except for techaical specification changes which were issued on September 11, 1991.

I-The September 16, 1992, Refueling Outage Summary indicates.that all hardware-related modifications have been implemented for Unit 1. . Accordingly, all actions associated with TAC No. M69730 for Calvert Cliffs Unit I have been L implemented.

Modifications _to correct Control Room Human Enaineering Deficiencies. Calvert

' Cliffs Unit 1 (TAC No. M561iO) and Unit 2 (TAC No. M561111-

The September 16, 1992, Refueling Outage Summary provides the status.of the l four remaining Unit 1 Human Engineering Deficiencies (HEOs) modifications as t

follows:

9212160298 921200 1400S0 Ejf  ? E d ZY e5M '

POR P^

ADOCK 05000317 PDR g..

( l ty  ;

• ^.

+p Seg e

'

• Nee On ,. ,

g ss .,

04 Op

/ , +

f 1

i

,*e s#:~(::: ,, : n . :4 n;>

o

% c. ,.,, v::,;,p

+,, &.A,y,9;+e %:;,., '$% q

.eip, s Er *::'c,," *h

^h^,,"^'; "

i;.k ,,,,A Ah '.

fi #";:,,w, qp!${

^

[s),s. 4 3,4 b ,

7.  :

s, .

a.,,s?y+:$+ze:4 s

4 feQp/g+;w;;.,+s,  :,

+

+

,,,hy% c t

%;%%s.%

^s~< y,

^*v,ps,,,',y,,g

• s,.

s, 4'.9:+,,% % O

. cy,, %

A, h p EO,,0, r. f:

,4 404 9

O 0,7.+/

~~~ fh

Mr. Robert E. Denton December 8, 1992 HED: Meters on plane B of panels 17,18, and 20 will be rearranged and/or broken up by demarcation or spacing techniques to enhance functional grouping.

Facility Change Request (FCR)88-208.

Status: As discussed in a letter to the staff dated March 6,1992, this FCR is cancelled. The electrical control panels will be replaced as the result of the installation of the new emergency diesel generators.

HED: All control room keylock switches not conforming to the standard position convention will be remounted. FCR 88-210.

Status: This HED has been downgraded from safety-related to nonsafety-related by BG&E and the FCR has been canceled. During a conference call between the NRC staff and licensee representatives on November 17, 1992, the cancellation of this FCR was discussed and the staff was satisfied with the justification.

The licensee has verified that operators had not experienced any problems with control room keylock switches and that the key could not get jammed if inserted improperly in the lock. No further action is required.

HEU: Control room lighting, which is provided during a loss of offsite AC, does not provide an illumination level of 10 foot-candles. The lighting will be enhanced for both the control room and the auxiliary shutdown panel (C43).

FCR 88-218.

Status: As discussed in a letter to the staff dated July 6, 1990, this modification is scheduled to be implemented before the Unit 2 restart from the 1993 refueling outage.

HED: Operator (s) have specified the need to add auxiliary feedwater (AFW) pump suction pressure indication to the control room. This indication will be added to control room panels 1/2 C04. FCR 88-225.

Status: This FCR has been canceled by BG&E. During a conference call between the NRC staff and licensee representatives on November 17, 1992, the cancellation of this FCR was discussed with the staff. There is a low suction pressure alarm in the control room and additional indications are displayed such as valve line-up, pump discharge pressure, and condensate storage tank level. The licensee and its operations staff have determined that adequate information relating to the status of the AFW system is available. No further action is required.

Based on the above status, all HEDs identified during the Detailed Control Room Design Review will be dispositioned or implemented prior to the restart of Unit 2 from its spring 1993 refueling outage.

l

tobert E. Denton December 8, 1992 hsideration of ASME oc de Reoair of Pioe Flaw. Calvert Cliffs Unit 1 (TAC 281522) tter dated April 25, 1991, BG&E requested relief from the ASME Code rements for the repair of a through-wall flaw on a Code Class 3 piping e saltwater header system. By letter dated May 17, 1991, the NRC staff ed the relief and approved the non-Code repair until the next refueling e at which time Code repair or replacement would be made. The mber 16, 1992, Refueling Outage Summary indicates that the header was ced with new pipe during the 1992 outage. Therefore, all actions lated with TAC No. M81522 for Calvert Cliffs Unit I have been mented.

lical Specification amendment to isolation valve surveillance reauirement fit 1(TACNo.M82363)

\cember 22, 1991, safety injection tank isolation valve M0V-644 which had closed to perform repairs on the safety injection system failed to in . The valve stem was found to be bent. Temporary corrective action sted of welding the valve stem to the valve yoke which resulted in the t

remaining permanently opened. Verification of valve position as red by technical specifications was no longer needed until the valve be repaired or replaced. On January 29, 1992, Amendment No. 167 added a

)otetoexemptmotor-operatedv;1veMOV-644fromthesurveillance rement to verify open position.

.eptember 16, 1992, Refueling Outage Summary indicates that MOV-644 was red during the 1992 refueling outage. The footnote added by Amendment 67 is no longer applicable. Therefore, all actions associated with TAC j82363forUnitIhavebeenimplemented. The footnote will be removed by I

sequent administrative amendment request and a new TAC number will be d to track the review.

.ase in auxiliary feedwater actuation delay time for Unit 1 (TAC No.

ill

' ment No.149 and Amendment No.130 for Units 1 and 2, respectively, ed the auxiliary feedwater (AFW) actuation delay time from 54.5 seconds

,0 seconds. By letter dated October 9, 1991, BG&E informed the NRC staff

-implementation of this amendment had permitted modifications to Unit 2 admission system which resulted in substantial improvements in system bility, eptember 16, 1992, Refueling Outage Summary indicates that similar ications to Unit 1 steam admission system had been implemented during the outage. Therefore, all actions associated with TAC Ho. M72075 for Unit I been implemented.

Mr. Robert E. Denton December 8, 1992 HED: Meters on plane B of panels 17,18, and 20 will be rearranged and/or broken up by demarcation or spacing techniques to enhance functional grouping.

Facility Change Request (FCR)88-208.

Status: As discussed in a letter to the staff dated March 6, 1992, this FCR is cancelled. The electrical control panels will be replaced as the result of the installation of the new emergency diesel generators-HED: All control room keylock switches not conforaing to the standard position convention will be remounted. FCR 88-210.

Status: This HED has been downgraded from safety-related to non>?fety-related by BG&E and the FCR has been canceled. During a conference call be m en the NRC staff and licensee representatives on November 17, 1992, the canceilation of this FCR was discussed and the staff was satisfied with the justification.

The licensee has verified that operators had not experienced any problems wit.h control room keylock switches and that the key could not get jammed if inserted improperly in the lock. No further action is required.

HED: Control room lighting, which is provided during a loss of offsite AC, does not provide an illumination level of 10 foot-candles. The lighting will be enhanced for both the control room and the auxiliary shutdown panel (C43).

j FCR 88-218.

I Status: As discussed in a letter to the staff dated July 6,1990, this modification is scheduled to be implemented before the Unit 2 restart from the 1993 refueling outage.

HED: Operator (s) havn specified the need to add auxiliary feedwater (AFW) pump suction pressure indication to the control room. This indication will be added to control room panels 1/2 C04. FCR 88-225.

Status: This FCR has been canceled by BG&E. During a conference call between the NRC staff and licensee representatives on November 17, 1992, the cancellation of this FCR was discussed with the staff. There is a low suction pressure alarm in the control room and additional indications are displayed such as valve line-up, pump discharge pressure, and condensate storage tank level. The licensee and its operations staff have determined that adequate information relating to the status of the AFW system is available. No further action is required.

Based on the above status, all HEDs identified during the Detailed Control Room Design Review will be dispositioned or implemented prior to the restart of Unit 2 from its spring 1993 refueling outage.

Mr. Robert E. Denton December 8,1992 Reconsideration of ASME Code Reoair of Ploe Flaw. Calvert Cliffs Unit 1 (TAC No. M81522)

By letter dated April 25, 1991, BG&E requested relief from the ASME Code requirements for the repair of a through-wall flaw on a Code Class 3 piping of the saltwater header system. By letter dated May 17, 1991, the NRC staff granted the relief and approved the non-Code repair until the next refueling outage at which time Code repair or replacement would be made. The September 16, 1992, Refueling Outage Summary indicates that the header was replaced with new pipe during the 1992 outage. Therefore, all actions associated with TAC No. M81522 for Calvert Cliffs Unit I have been implemented.

Igchnical Specification amendment to isolation valve surveillance reauiremgni for Unit 1 (TAC No. M82363)

On December 22, 1991, safety injection tank isolation valve MOV-644 which had been closed to perforh. repairs on the safety injection system failed to reopen. The valve stem was found to be bent. Temporary corrective action consisted of welding the valve stem to the valve yoke which resulted in the valve remaining permanently opened. Verification of valve position as required by technical specifications was no longer needed until the valve could be repaired or replaced. On January 29, 1992, Amendment No. 167 added a

, footnote to exempt motor-operated valve H0V-644 from the surveillance

, requirement to verify open position.

The September 16, 1992, Refueling Outage Summary indicates that M0V-644 was repaired during the 1992 refueling outage. The footnote added by Amendment No.161 is no longer applicable. Therefore, all actions associated with TAC No. M82363 for Unit I have been implemented. The footnote will be removed by a subsequent administrative amendment request and a new TAC number will be issued to track the review.

Increase in auxiliary feedwater actuation delay time for Unit 1 (TAC No.

M72075)

Amendment No. 149 and Amendment No. 130 for Units 1 and 2, respectively, changed the auxiliary feedwater (AFW) actuation delay time from 54.5 seconds to 180 seconds. By letter dated October 9, 1991, BG&E informed the NRC staff that implementation of this amendment had permitted modifications to Unit 2 steam admission system which resulted in substantial improvements in system reliability.

The September 16, 1992, Refueling Outage Summary indicates that similar modifications to Unit I steam admission system had been implemented during the 1992 outage. Therefore, all actions associated with TAC No. M72075 for Unit 1

have been implemented, i

l l

l

\

i Mr. Robert E. Denton December 8, 1992 Station Blackout modification status for Unit 1 (TAC No. M68525) and Unit 2 (TAC No. M68526)

The September 16, 1992, Refueling Outage Sumary indicates that two of the SB0 modifications BG&E has comitted to perform on Unit I have been completed during the 1992 refueling outage. These modifications consist of providing DC-powered indication for some Unit 1 isolation valves and providing AC power (through the inverters) to the reactor vessel level monitoring system. The staff understands that the remaining Unit 1 modifications are the following:

(1) open up portions of the control room drop ceiling and (2) add temperature indicating switches to the battery room.

The Refueling Outage Sumary also indicates that the remaining SB0 modifications on Units 1 and 2, with the exception of the diesel generator addition, are scheduled to be performed before the end of Unit 2 refueling outage in 1993. The addition of new emergency diesel generators is scheduled for completion in 1996.

Containment oressure instrument tubino nodifications on Unit 1 (TAC No.

M79911) and Unit 2 (TAC No. M79912)

By letter dated December 30, 1991, the NRC staff provided an evaluation of the modifications to the containment pressure instrument tubing lines supports as proposed by BG&E in response to concerns raised by the staff. The staff concluded that the seismic analysis methodology used by BG&E in support of the modifications was unacceptable and providad options to resolve this issue. By letter dated February 3,1992, BG&E proposed to reanalyze the tubing lines by using a methodology acceptable to the staff and to modify the tubing lines accordingly. The staff found the reanalysis, modifications, and modification schedule acceptable, The September 16, 1992, Refueling Outage Sumary indicates that Unit I modifications which could not be performed during power operation have been completed. Therefore, all actions associated with TAC No. M79911 have been implemented. Similar modifications are to be implemented on Unit 2 during the next refueling outage scheduled for the spring of 1993.

Sincerely,

.5 -

Daniel G. Mcdonald, Senior Project Manager Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc: See next page

.. - .- ... ..~. . - - - - . - - - -. . .. - - _. - . - ..-.- . .-

Mr. Robert E. Denton Calvert Cliffs ~ Nuclear Power Plant Baltimore Gas & Electric Company Unit Nos. I and 2 cc:

Mr. Michael Moore, President Mr. Joseph H. Walter Calvert County Board of Engineering Division .

Commissioners Public Service Commission of 175 Main Street Maryland Prince Frederick, Maryland 20678 American Building 231 E. Baltimore Street D. A. Brune, Esquire -

Baltimore, Maryland 21202-3486 General Counsel Baltimore Gas and Electric Company '

Kristen A. Burger, Esquire P. O. Box 1475 . . Maryland People's Counsel Baltimore, Maryland 21203 American Building, 9th Floor 231 E. Baltimore Street Jay E. Silberg, Esquire Baltimore, Maryland 21202 Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW Patricia T. Birnie, Esquire Washington, DC 20037- - Co-Director Maryland. Safe Energy Coalition Mr. G. L. Detter, Director, -tHui P. O. Box 33111 Calvert Cliffs Nuclear Power-Plant Baltimore, Maryland ~21218 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-47027 Resident Inspector c/o U.S. Nuclear Regulatory 1 Commission l P. O. BoxL287 l St. Leonard, Maryland 20685

! Mr. Richard I.'McLean

Administrator - Radioecology Department of Natural . Resources

, -580 Taylor Avenue.

l Tawes State Office Building

!. B3 Annapolis, Maryland 21401 i .-

l' Regional Administrator, Region I i U.S. Nuclear Regulatory Commission r 475 Allendale Road L.

g King of Prussia, Pennsylvania 19406 P

l s-I u

..e,, . . . , c.h . , E h , . d.. . . + . . - - . - . , ., .- --- ,.b ,.w,, , .-m,,,...,, ,L,.-w.,,..,.,,,,,.~4 .+.m J.,..--,,,,,,.,.e.,, +w, . . . , ,rw-,.e. , - . - .

. Mr. Robert E. Denton December 8, 1992 S_tation Blackout modification status for Unit 1 (TAC No. M68525) and Unit 2 (TAC No M68526)

The September 16, 1992, Refueling Outage Summary indicates that two of the 500 modifications BG&E has committed to perform on Unit I have been completed during the 1992 refueling outage. These modifications consist of providing DC-powered indication for some Unit 1 isolation valves and providing AC power (through the inverters) to the reactor vessel level monitoring system. The staff understands that the remaining Unit 1 modifications are the following:

(1) open up portions of the control room drop ceiling and (2) add temperature indicating switches to the battery room.

The Refueling Outage Summary also indicates that the remaining SB0 modifiutions on Units 1 and 2, with the exception of the diesel generator addition, are scheduled to be performed before the end of Unit 2 refueling s outage in 1993. The addition of new emergency diesel generators is scheduled for completion in 1996.

Containment pressure instrument tubina modifications on Unit 1 (TAC No, M79911) and Unit 2 (TAC No. M79912)

By letter dated December 30, 1991, the NRC staff provided an evcluation of the modifications to the containment pressure instrument tubing lines supports as proposed by BG&E in response to concerns raised by the staff. The staff concluded that the seismic analysis methodology used by BG&E in support of the modifications was unacceptable and provided options to resolve this issue. By letter dated February 3,1992, BG&E proposed to reanalyze the tubing lines by using a methodology acceptable to the staff and to modify the tubing lines accordingly. The staff found the reanalysis, modifications, and modification schedule acceptable.

The September 16, 1992, Refueling Outage Sumary indicates that Unit 1 modifications which could not be performed during power operation have been completed. Therefore, all actions associated with TAC No. M79911 have been implemented. Similar modifications au to be implemoc'ed on Unit 2 during the next refueling outage scheduled for the spring of 1993.

Sincerely, Original signed by:

Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l Divisiui, cf Peactor Projects - :/II Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:

LDocket File-. NRC & Local PDRs PDI-l Reading SVarga JCalvo RACapra CVogan DMcDonald C0rsini D0udinot OGC ACRS (10)

CCowgill, RGN-1 Plant File f o m cE PDI-1:LS PDI-hPF., PDI-1: Mb PDI-1:D WE CVogan d 00iibnot: avl DMcDonald RAcapra OATE G/1/92 /R /8 92

/ 12 / 6 92 & /9/92 / /  !

0FFICIAL RECORD COPY FILENAME: G:\CCl-2\CC169730.LTR

. - _ .