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{{#Wiki_filter:.. e Public Service Electric an*d Gas Company P.O. Box 236. Hancocks Bridge, N\3W Jersey 08038 Salem Generating Station U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555  
{{#Wiki_filter:e
..         PS~G Public Service Electric an*d Gas Company P.O. Box 236. Hancocks Bridge, N\3W Jersey 08038
                                                                                                                    . i Salem Generating Station November 19, 1992 U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC               20555


==Dear Sir:==
==Dear Sir:==
SALEM GENERATING STATION LICENSE NO. DPR-iO DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-022-00 November 19, 1992 This Licensee Event requirements of the 50. 73 (a) (2) (i) (A). thirty (30) days of Report is being submitted pursuant to the Code of Federal Regulations lOCFR MJP:pc Distribution
 
;9211300223 921130 S PDR ADOCK 05000272 PnP* This report is required to be issued within event discovery.
SALEM GENERATING STATION LICENSE NO. DPR-iO DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-022-00 This Licensee Event               Report is being submitted pursuant to the requirements of the               Code of Federal Regulations 10CFR
Sincerely
: 50. 73 (a) (2) (i) (A).           This report is required to be issued within thirty (30) days of                event discovery.
: yours, l{ttKJ-c. A Vondra *. General Manager -Salem Operations . i i2-ss NRC FORM 366 *U.S. NUCLEAR REGULATORY COMMISSION (6-89) APPROVED OMB NO. 3150-0104 EXPIRES: 4/30/92 . ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH* THIS LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD . COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, .AND TO THE. PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FACILITY NAME (11 I DOCKET NUMBER 121 I PAGE 131 Salem Generating Station -Unit 1 o 1s1010101217 .I 2 J 1 OF 0 13 TITLE (41 Controlled Shutdown to eomply with Technical Specification Action Statement
Sincerely yours,
: 3. 7 .* 4 .1. EVENT DATE (5) LER NUMBER (6) REPORT DATE 171 OTHER FACILITIES INVOLVED (81 MONTH DAV VEAR VEAR :::::::::::
                                                                  *~.*
SEQUENTIAL
l{ttKJ-
){ REVlSION MONTH DAV VEAR FAc;I LITY NAMES DOCKET NUMBERISI NUMBER NUMBER OJ5JOJOJOI I I 1 lo 217 9! 2 -I 2 l2 -ol 111 11 9 91 9 2 0 0 2 0 I 5 I 0 I 0 I 0 I I I OPERATING THIS REPORT IS SUBMITTED*PURSUANT TO THE OF 10 CFR §: (Chock on* or moro of th* following}
: c. A Vondra General Manager -
(11) MODE 18) 2 20.402(bl 20.405(cl 50.73(1)(2)(ivl 73.71lbl I ---POWER 20.40611111  
Salem Operations MJP:pc Distribution
)(i) 50.38(c)(1) 50.73(1l121M . 73.71(cl LEVEL ----1101 I I 20.405111(1 lliil 50.38lcll2l 50.7311112) (viii OTHER (Spocify in Abstroct --btJ(ow and in Text, NRC Form 20.406(1)(1 llilil x 60.73(1ll211il 60.7311112llviiillAI 366AI ,____ --20.40611111  
    ;9211300223 921130                                                                        es-2~asi rsr.~1 i2-ss PDR ADOCK 05000272 S                          PnP*
)(Iv) 50.731*ll2lliil 50.7l(1)(2llvliillBl --20.4061*111 llvl 50.7311112lliiil 50.731111211*1 LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M.. ,J. Pollack -LER Coordinator 610 19 313 19 I -12 p 1212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 .*.;.*.*.
 
...... * . ... , ..... ,.* ... , -:*:*:*:*
NRC FORM 366                                                                     *U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-89)
MANUFAC-REPORTABLE  
            ~
;.;.; *:*;.*;* *:*::*;-MANUFAC* REPORTABLE  
EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH* THIS
<:> ...... ,. . .... ,. *.*:* ... . ... *.;. CAUSE SYSTEM
                              .      LICENSEE EVENT REPORT (LERI                                                                                             INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, .AND TO THE. PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE FACILITY NAME (11 Salem Generating Station                                    - Unit 1 I
* COMPONENT TUR ER TO*NPRDS . ;.*.*.;. ;.; . CAUSE SYSTEM COMPONENT TUR ER TO NPRDS .;.*.;.* .. ,, ,',",', ;.: *:*. .*:* *.*.*.* . . * .. :*.* ;-;* .... ,',' ;:;: *.*: *.;. *:*; *.* .. *:* .... :.* . .... *.*. ;.;. *:*: . ;.; I I I I I I I ;.; :*:* .*.* :*.* *.*. I . I I I I . I I .... .::; :*:*=*=* *.*. *.;. ,:.; *.*. .;.* ;.;. ..... ;.;., ..... *.* . ., .. ,.; ...... *. *.*.:::-;.;
OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
.... ; :-:*::*:*
DOCKET NUMBER 121 o 1s1010101217               .I 2 J 1 I                PAGE 131 OF 0                     13 TITLE (41 Controlled Shutdown to eomply with Technical Specification Action Statement 3. 7.* 4 .1.
.;.;:.*. ,',' .; .. ;.; I . *.* .*.* ;*.**:.:.;.;*.* . f;.; .. *.* *.*. ;.;. *.* ..
EVENT DATE (5)                             LER NUMBER (6)                                 REPORT DATE 171                                               OTHER FACILITIES INVOLVED (81 SEQUENTIAL MONTH       DAV       VEAR     VEAR   :::::::::::     NUMBER  ){ REVlSION NUMBER MONTH DAV                 VEAR                 FAc;I LITY NAMES                   DOCKET NUMBERISI OJ5JOJOJOI                                     I             I 1 lo       217         9 2      9! 2
* I I I 1-I I ........ ... **:*:::*:****
                                          -           0  I 2 l2 -     ol 0 111                               11 9 91 2                                                                   0 I 5I0 I 0 I 0 I                               I             I OPERATING THIS REPORT IS SUBMITTED*PURSUANT TO THE R~QUIREMENTS OF 10 CFR                                               &sect;: (Chock on* or moro of th* following} (11)
I I I I I I I :::: :::::::: :::::::: ?\ SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY* YEAR bi NO EXPECTED SUBMISSION n YES (If yos, EXPECTED SUBMISSION DATE} DATE (151 I I I ABSTRACT (Limir to '400 spaces, i.e .. tJpproximately fifrtum sing/e.space lines} (16)
MODE 18) 2       20.402(bl                                       20.405(cl                                                     50.73(1)(2)(ivl                           73.71lbl I                                                                                                                                                                         -
* On October 27, 1992 at 1815 hours, a controlled shutdown from Mode 2 was commenced in anticipation of an inability to meet 72-hour time requirement of Technical Specification Action statement 3.7.4.1 which was entered when 12 Service Water (SW} header was removed from.service to replace a pipe section whose walls had shown indication of thinning per ultrasonic examination.
POWER                             20.40611111 )(i)                                 50.38(c)(1)                                                   50.73(1l121M .                           73.71(cl LEVEL                       -                                         -                                                                 -
The Unit was placed in Mode 2 on October. 24, 1992 for repair of a packing leak on the 12BF19 f eedwater valve. Although a Safety -Evaluation had documented the abs.ence
1101           I   I         20.405111(1 lliil
                                                                          ~
50.38lcll2l
                                                                                                                                              -      50.7311112) (viii OTHER (Spocify in Abstroct btJ(ow and in Text, NRC Form l l~l1l l l l l l lil l l l l 20.406(1)(1 llilil                     x       60.73(1ll211il                                                 60.7311112llviiillAI                     366AI 20.40611111 )(Iv)
                                                                          -          50.731*ll2lliil
                                                                                                                                              -      50.7l(1)(2llvliillBl
                                ~
20.4061*111 llvl
                                                                          -          50.7311112lliiil
                                                                                                                                              -      50.731111211*1 LICENSEE CONTACT FOR THIS LER 1121 NAME                                                                                                                                                                                     TELEPHONE NUMBER AREA CODE M.. ,J. Pollack             -   LER Coordinator                                                                                                                         610 19         313 19 I -12 p 1212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC-       REPORTABLE       ;.;.;       *:*;.*;* *:*::*;-                                                         MANUFAC*         REPORTABLE CAUSE   SYSTEM
* COMPONENT                                                               .;.*.*.;.         .             CAUSE SYSTEM       COMPONENT                                                                                         ,',",',
TUR ER      TO*NPRDS TUR ER          TO NPRDS      *.*.*.*. .*.. :*.* ;-;*     ....
                                                                                                        .*.*                 *.*.                                                                           .... .::;                          :*:*=*=*
I         I   I   I                 I   I   I                 ;.;                             :*.*
                                                                                                                              *.*.           I         .I     I   I       I .I     I                     *.;.           ,:.; *.*.           .;.*
f;.; .. *.*
I          I I     I                 1- I     I                                                                             I           I     I   I       I   I   I                   :::: ::::::::                   :::::::: ?\
SUPPLEMENTAL REPORT EXPECTED 1141                                                                                                         MONTH               DAY*                   YEAR EXPECTED n       YES (If yos, co~plot* EXPECTED SUBMISSION DATE}                                         bi ABSTRACT (Limir to '400 spaces, i.e .. tJpproximately fifrtum sing/e.space typ~writttJn lines} (16)
* NO SUBMISSION DATE (151 I                      I                        I On October 27, 1992 at 1815 hours, a controlled shutdown from Mode 2 was commenced in anticipation of an inability to meet th~ 72-hour time requirement of Technical Specification Action statement 3.7.4.1 which was entered when 12 Service Water (SW} header was removed from.service to replace a pipe section whose walls had shown indication of thinning per ultrasonic examination. The Unit was placed in Mode 2 on October.
24, 1992 for repair of a packing leak on the 12BF19 f eedwater regulati~g valve.                                     Although a Safety -Evaluation had documented the abs.ence
* of an immediate SW system operability concern, management decided to replace the pipe section in the current plant condition.
* of an immediate SW system operability concern, management decided to replace the pipe section in the current plant condition.
Pipe section replacement required the removal from service of 12 Service Water header which occurred at 0346 hours on October 25. The initial job duration estimate .anticipated work completion-prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered preventing work completion prior to the expiration of the 72-hour allowance at 0346 on October 28. A Unit cool down was commenced toward Cold Shutdown.
      ~
Repairs to the 12 Service Water header were completed at 0215 hours on October 29. Cooldown was secured prior . to entry into Mode 4 (Hot Shutdown).
Pipe section replacement required the removal from service of 12 Service Water header which occurred at 0346 hours on October 25. The initial job duration estimate .anticipated work completion-prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered preventing work completion prior to the expiration of the 72-hour allowance at 0346 on October 28. A Unit cool down was commenced toward Cold Shutdown. Repairs to the 12 Service Water header were completed at 0215 hours on October 29. Cooldown was secured prior .to entry into Mode 4 (Hot Shutdown). The root cause of this occurrence is "Other".
The root cause of this occurrence is "Other". As discussed above, emergent work prevented return of 12 Service Water heaQ.er to service within the required Action Statement time constraint.
As discussed above, emergent work prevented return of 12 Service Water heaQ.er to service within the required Action Statement time constraint.
NRC Form 366 (6-J91
NRC Form 366 (6-J91
-.e -' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:
 
Westinghouse  
                                                -.e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station       DOCKET NUMBER    LER NUMBER        PAGE Unit 1                           5000272         92-022-00        2 of 3 PLANT AND SYSTEM IDENTIFICATION:
-Pressurized Water Reactor LER NUMBER 92-022-00 PAGE 2 of 3 Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:
Westinghouse   - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}
Controlled Shutdown to comply with Technicai Specification Action statement 3.7.4.1. Event Date: 10/27/92 Report Date: 11/19/92 This report was initiated by Incident Report No *. 92-695. CONDITIONS PRIOR TO OCCURRENCE:-
IDENTIFICATION OF OCCURRENCE:
Controlled Shutdown to comply with Technicai Specification Action statement 3.7.4.1.
Event Date:   10/27/92 Report Date:   11/19/92 This report was initiated by Incident Report No *. 92-695.
CONDITIONS PRIOR TO OCCURRENCE:-
Mode 2 {Startup)
Mode 2 {Startup)
DESCRIPTION OF OCCURRENCE:
DESCRIPTION OF OCCURRENCE:
On 27, 1992 at 1815 hours, a controlled shutdown from Mode 2 was commenced in-anticipation of an inability to meet the 72-hour time requirement of Technical Specification Action Statement 3.7.4.1. The Technical Specification Action statement was entered when 12 Service Water header was removed from service to replace a section of piping whose walls had shown indication of thinning due to erosion/corrosion.
On Octob~r 27, 1992 at 1815 hours, a controlled shutdown from Mode 2 was commenced in-anticipation of an inability to meet the 72-hour time requirement of Technical Specification Action Statement 3.7.4.1. The Technical Specification Action statement was entered when 12 Service Water header was removed from service to replace a section of piping whose walls had shown indication of thinning due to erosion/corrosion.
The Unit was placed in Mode 2 on October 24; 1992 for repair of a packing leak on the 12BF19 feedwater regulating valve. While in Mode 2, the decision was made to repair other items that could challenge plant operation during the operating cycle. This included replacement of the Service Water (SW) {BI} pipe section downstream of the 12SW387 valve. This section had shown indications of wall thinning from . recent ultrasonic examinations.
The Unit was placed in Mode 2 on October 24; 1992 for repair of a packing leak on the 12BF19 feedwater regulating valve. While in Mode 2, the decision was made to repair other items that could challenge plant operation during the operating cycle. This included replacement of the Service Water (SW) {BI} pipe section downstream of the 12SW387 valve. This section had shown indications of wall thinning from .
Although a Safety Evaluation had documented the absence of an immediate operability concern, management  
recent ultrasonic examinations. Although a Safety Evaluation had documented the absence of an immediate operability concern, management
*decided to replace the pipe section in the current plant condition.
    *decided to replace the pipe section in the current plant condition.
The tagging boundaries to support replacement required the removal from service of 12 Service Water header, necessitating entry into the 72-hour Action Statement at 0346 hours on October 25. The initial job duration estimate anticipated work completion prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered during pipe fit-up due to inside diameter mismatch between the existing pipe and the new pipe section. This required the welding and grinding of a taper to provide a .smooth transition on the inside of the pipe. The work could not be completed prior to the expiration of the 72-hour allowance at 0346 on October 28,_and a Unit cooldown was commenced toward Cold Shutdown.
The tagging boundaries to support replacement required the removal from service of 12 Service Water header, necessitating entry into the 72-hour Action Statement at 0346 hours on October 25. The initial job duration estimate anticipated work completion prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered during pipe fit-up due to inside diameter mismatch between the existing pipe and the new pipe section. This required the welding and grinding of a taper to provide a .smooth transition on the inside of the pipe. The work could not be completed prior to the expiration of the 72-hour allowance at 0346 on October 28,_and a Unit cooldown was commenced toward Cold Shutdown.
. . LICENSEE EVENT REPORT (LER)' TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 DESCRIPTION OF OCCURRENCE: (cont'd) LER NUMBER 92-022-00 PAGE 3 of 3 Repairs to the 12 Service Water header were completed at 0215 hours on
 
* October 29. Cooldown was secured prior to entry into Mode 4 (Hot Shutdown).
          . .       LICENSEE EVENT REPORT (LER)' TEXT CONTINUATION Salem Generating Station           DOCKET NUMBER      LER NUMBER    PAGE Unit 1                               5000272         92-022-00    3 of 3 DESCRIPTION OF OCCURRENCE:       (cont'd)
Plant heatup commenced at 0330 on October 29 and the Unit .was synchronized to the grid at 2316 on November 1, 1992. Technical Specification 3.7.4.1 states: "At least two independent service water loops shall be OPERABLE." Technical Specification 3.7.4.1 Action states: "With only one service water loop OPERABLE, restore at least two loops to-OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours." APPARENT CAUSE OF OCCURRENCE:
Repairs to the 12 Service Water header were completed at 0215 hours on
The root cause of this o_ccurrence is "Other", per NUREG 1022, "Licensee Event Report System". As discussed above, emergent work prevented return of 12 Service Water header to service within the required Action Statement time constraint.
* October 29. Cooldown was secured prior to entry into Mode 4 (Hot Shutdown). Plant heatup commenced at 0330 on October 29 and the Unit
Consequently, the Unit entered Mode 3. ANALYSIS OF OCCURRENCE:
    .was synchronized to the grid at 2316 on November 1, 1992.
The operability of the Service Water System ensures that sufficient cooling capacity exists _for continued operation of safety related equipment during normal and accident conditions.
Technical Specification 3.7.4.1 states:
The redundant cooling capacity of this system, assuming a single failure, is . *consistent with the assumptions used in the accident analyses.
            "At least two independent service water loops shall be OPERABLE."
In this event,.the other SW loop remained available.
Technical Specification 3.7.4.1 Action states:
The requirements of the Technical Specification Action statement were met. Therefore, this event did not affect the health or safety of the public. This event is reportable to the NRC in accordance wi.th lOCFR 50. 73 (a) (2) (i) (A). CORRECTIVE ACTION: The Service Water pipe section was replaced and the system returned to service. MJP:pc SORC Mtg. 92-116 General Manager Salem Operations}}
            "With only one service water loop OPERABLE, restore at least two loops to-OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours."
APPARENT CAUSE OF OCCURRENCE:
The root cause of this o_ccurrence is "Other", per NUREG 1022, "Licensee Event Report System". As discussed above, emergent work prevented return of 12 Service Water header to service within the required Action Statement time constraint. Consequently, the Unit entered Mode 3.
ANALYSIS OF OCCURRENCE:
The operability of the Service Water System ensures that sufficient cooling capacity exists _for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is .
  *consistent with the assumptions used in the accident analyses.
In this event,.the other SW loop remained available. The requirements of the Technical Specification Action statement were met. Therefore, this event did not affect the health or safety of the public. This event is reportable to the NRC in accordance wi.th 10CFR
: 50. 73 (a) (2) (i) (A).
CORRECTIVE ACTION:
The Service Water pipe section was replaced and the system returned to service.
p{L;#~L General Manager ~
Salem Operations MJP:pc SORC Mtg. 92-116}}

Latest revision as of 10:38, 23 February 2020

LER 92-022-00:on 921027,controlled Shutdown from Mode 2 Commenced in Anticipation of Inability to Meet 72 H TS Time Requirement.Caused by Emergent Work Preventing Return of 12 Svc Water Header to Svc.Pipe Section replaced.W/921119 Ltr
ML18096B116
Person / Time
Site: Salem PSEG icon.png
Issue date: 11/19/1992
From: Pollack M, Vondra C
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-022, LER-92-22, NUDOCS 9211300223
Download: ML18096B116 (4)


Text

e

.. PS~G Public Service Electric an*d Gas Company P.O. Box 236. Hancocks Bridge, N\3W Jersey 08038

. i Salem Generating Station November 19, 1992 U. s. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR-iO DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 92-022-00 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR

50. 73 (a) (2) (i) (A). This report is required to be issued within thirty (30) days of event discovery.

Sincerely yours,

  • ~.*

l{ttKJ-

c. A Vondra General Manager -

Salem Operations MJP:pc Distribution

9211300223 921130 es-2~asi rsr.~1 i2-ss PDR ADOCK 05000272 S PnP*

NRC FORM 366 *U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 3150-0104 (6-89)

~

EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH* THIS

. LICENSEE EVENT REPORT (LERI INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530). U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, .AND TO THE. PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE FACILITY NAME (11 Salem Generating Station - Unit 1 I

OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

DOCKET NUMBER 121 o 1s1010101217 .I 2 J 1 I PAGE 131 OF 0 13 TITLE (41 Controlled Shutdown to eomply with Technical Specification Action Statement 3. 7.* 4 .1.

EVENT DATE (5) LER NUMBER (6) REPORT DATE 171 OTHER FACILITIES INVOLVED (81 SEQUENTIAL MONTH DAV VEAR VEAR  ::::::::::: NUMBER ){ REVlSION NUMBER MONTH DAV VEAR FAc;I LITY NAMES DOCKET NUMBERISI OJ5JOJOJOI I I 1 lo 217 9 2 9! 2

- 0 I 2 l2 - ol 0 111 11 9 91 2 0 I 5I0 I 0 I 0 I I I OPERATING THIS REPORT IS SUBMITTED*PURSUANT TO THE R~QUIREMENTS OF 10 CFR §: (Chock on* or moro of th* following} (11)

MODE 18) 2 20.402(bl 20.405(cl 50.73(1)(2)(ivl 73.71lbl I -

POWER 20.40611111 )(i) 50.38(c)(1) 50.73(1l121M . 73.71(cl LEVEL - - -

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- 50.731111211*1 LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE M.. ,J. Pollack - LER Coordinator 610 19 313 19 I -12 p 1212 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 MANUFAC- REPORTABLE  ;.;.; *:*;.*;* *:*::*;- MANUFAC* REPORTABLE CAUSE SYSTEM

  • COMPONENT .;.*.*.;. . CAUSE SYSTEM COMPONENT ,',",',

TUR ER TO*NPRDS TUR ER TO NPRDS *.*.*.*. .*..  :*.* ;-;* ....

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SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY* YEAR EXPECTED n YES (If yos, co~plot* EXPECTED SUBMISSION DATE} bi ABSTRACT (Limir to '400 spaces, i.e .. tJpproximately fifrtum sing/e.space typ~writttJn lines} (16)

  • NO SUBMISSION DATE (151 I I I On October 27, 1992 at 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />, a controlled shutdown from Mode 2 was commenced in anticipation of an inability to meet th~ 72-hour time requirement of Technical Specification Action statement 3.7.4.1 which was entered when 12 Service Water (SW} header was removed from.service to replace a pipe section whose walls had shown indication of thinning per ultrasonic examination. The Unit was placed in Mode 2 on October.

24, 1992 for repair of a packing leak on the 12BF19 f eedwater regulati~g valve. Although a Safety -Evaluation had documented the abs.ence

  • of an immediate SW system operability concern, management decided to replace the pipe section in the current plant condition.

~

Pipe section replacement required the removal from service of 12 Service Water header which occurred at 0346 hours0.004 days <br />0.0961 hours <br />5.720899e-4 weeks <br />1.31653e-4 months <br /> on October 25. The initial job duration estimate .anticipated work completion-prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered preventing work completion prior to the expiration of the 72-hour allowance at 0346 on October 28. A Unit cool down was commenced toward Cold Shutdown. Repairs to the 12 Service Water header were completed at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> on October 29. Cooldown was secured prior .to entry into Mode 4 (Hot Shutdown). The root cause of this occurrence is "Other".

As discussed above, emergent work prevented return of 12 Service Water heaQ.er to service within the required Action Statement time constraint.

NRC Form 366 (6-J91

-.e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-022-00 2 of 3 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}

IDENTIFICATION OF OCCURRENCE:

Controlled Shutdown to comply with Technicai Specification Action statement 3.7.4.1.

Event Date: 10/27/92 Report Date: 11/19/92 This report was initiated by Incident Report No *.92-695.

CONDITIONS PRIOR TO OCCURRENCE:-

Mode 2 {Startup)

DESCRIPTION OF OCCURRENCE:

On Octob~r 27, 1992 at 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />, a controlled shutdown from Mode 2 was commenced in-anticipation of an inability to meet the 72-hour time requirement of Technical Specification Action Statement 3.7.4.1. The Technical Specification Action statement was entered when 12 Service Water header was removed from service to replace a section of piping whose walls had shown indication of thinning due to erosion/corrosion.

The Unit was placed in Mode 2 on October 24; 1992 for repair of a packing leak on the 12BF19 feedwater regulating valve. While in Mode 2, the decision was made to repair other items that could challenge plant operation during the operating cycle. This included replacement of the Service Water (SW) {BI} pipe section downstream of the 12SW387 valve. This section had shown indications of wall thinning from .

recent ultrasonic examinations. Although a Safety Evaluation had documented the absence of an immediate operability concern, management

  • decided to replace the pipe section in the current plant condition.

The tagging boundaries to support replacement required the removal from service of 12 Service Water header, necessitating entry into the 72-hour Action Statement at 0346 hours0.004 days <br />0.0961 hours <br />5.720899e-4 weeks <br />1.31653e-4 months <br /> on October 25. The initial job duration estimate anticipated work completion prior to expiration of the Action Statement time limitation, assuming only minor emergent work. Significant emergent work was encountered during pipe fit-up due to inside diameter mismatch between the existing pipe and the new pipe section. This required the welding and grinding of a taper to provide a .smooth transition on the inside of the pipe. The work could not be completed prior to the expiration of the 72-hour allowance at 0346 on October 28,_and a Unit cooldown was commenced toward Cold Shutdown.

. . LICENSEE EVENT REPORT (LER)' TEXT CONTINUATION Salem Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-022-00 3 of 3 DESCRIPTION OF OCCURRENCE: (cont'd)

Repairs to the 12 Service Water header were completed at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> on

  • October 29. Cooldown was secured prior to entry into Mode 4 (Hot Shutdown). Plant heatup commenced at 0330 on October 29 and the Unit

.was synchronized to the grid at 2316 on November 1, 1992.

Technical Specification 3.7.4.1 states:

"At least two independent service water loops shall be OPERABLE."

Technical Specification 3.7.4.1 Action states:

"With only one service water loop OPERABLE, restore at least two loops to-OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />."

APPARENT CAUSE OF OCCURRENCE:

The root cause of this o_ccurrence is "Other", per NUREG 1022, "Licensee Event Report System". As discussed above, emergent work prevented return of 12 Service Water header to service within the required Action Statement time constraint. Consequently, the Unit entered Mode 3.

ANALYSIS OF OCCURRENCE:

The operability of the Service Water System ensures that sufficient cooling capacity exists _for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is .

  • consistent with the assumptions used in the accident analyses.

In this event,.the other SW loop remained available. The requirements of the Technical Specification Action statement were met. Therefore, this event did not affect the health or safety of the public. This event is reportable to the NRC in accordance wi.th 10CFR

50. 73 (a) (2) (i) (A).

CORRECTIVE ACTION:

The Service Water pipe section was replaced and the system returned to service.

p{L;#~L General Manager ~

Salem Operations MJP:pc SORC Mtg.92-116