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* Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 27, 1995 U. s. Nuclear Regulatory Comritission Document Control Desk Washington, DC 20555 Attn: Document Control Desk SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT NO. 95-002-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a)
OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 27, 1995 U. s. Nuclear Regulatory Comritission Document Control Desk Washington, DC 20555 Attn:         Document Control Desk SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT NO. 95-002-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i) (B).             Issuance of this report is required within thirty (30) days of event discovery.
(2) (i) (B). Issuance of this report is required within thirty (30) days of event discovery.
Sincerely, J. C. Summers General Manager -
SORC Mtg. 95-028 MJPJ:vs C Distribution LER File 9503310059 950327 PDR ADOCK 05000272 S PDR The po\\*er is in your hands. Sincerely, J. C. Summers General Manager -Salem Operations 95*2168 REV. 6/94
Salem Operations SORC Mtg. 95-028 MJPJ:vs C         Distribution LER File 9503310059 950327 PDR ADOCK 05000272 S                         PDR The po\\*er is in your hands.
.. I "NRC 17"0RM 366 . U.S. NUCLEAR REGULATORY COMMISSION ROVED BY OMB NO. 3150-0104 5*92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR
95*2168 REV. 6/94
* REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503. FAc1urvNAMEt11salem Generating Station -Unit 1 DOCKET NUMBER (2) 05000 272 PAGE (3) 1 OF 4 TITLE (4J Failure to Restore Automatic Control of Pressurizer Power Operated Relief Valve (PORV 1PR2 or Close Associated Block Valve 1PR7 Within One Hour -EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8) SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER NUMBER MONTH DAY YEAR 05000 02 24 95 95 002 00 03. 27. 95 FACILITY NAME DOCKET NUMBER ----.. .. 05000 OPERATING 3 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: .(Check one or more (11) MODE (9) 20.402(b) 20.405(c)
 
: 50. 73 (a)(2)(iv) 73.71(b) POWER 0% 20.405(a)(1  
I "NRC 17"0RM 366 5*92)
)(i) 50.36(c)(1)
LICENSEE EVENT REPORT (LER)
: 50. 73 (a)(2){v) 73.71(c) LEVEL (10) 20.405(a)(1)(ii) 50.36(0)(2) 50.73(a)(2)(vii)
                                                          . U.S. NUCLEAR REGULATORY COMMISSION                                     ROVED BY OMB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
OTHER 20.405(a)(1  
COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR FORWARD REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits/characters for each block)                       MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
)(iii) )( 50.73(a)(2){i)
FAc1urvNAMEt11salem Generating Station - Unit 1                                                               DOCKET NUMBER (2)                                     PAGE (3) 05000 272                          1 OF 4 TITLE (4J Failure to Restore Automatic Control of Pressurizer Power Operated Relief Valve (PORV 1PR2 or Close Associated Block Valve 1PR7 Within One Hour                                                                                   -
: 50. 73(a)(2)(viii)(A) (Specify in Abstract 20.405(a)(1)(iv) 50.73(a) (2) (ii) 50.73(a)(2){viii)(B) below and in Text, NRC Form 366A) 20.405(a)(1  
EVENT DATE (5)                         LER NUMBER (6                   REPORT     NUMBER     (7)                 OTHER     FACILITIES INVOLVED (8)
)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
FACILITY NAME                             DOCKET NUMBER SEQUENTIAL        REVISION                  DAY    YEAR MONTH         DAY       YEAR     YEAR           NUMBER           NUMBER     MONTH                                                                       05000 FACILITY NAME                      .. DOCKET NUMBER 02           24         95       95     --    002         --    00       03.       27.     95                                                     05000 OPERATING             3       THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: .(Check one or more (11)
MODE (9)                       20.402(b)                               20.405(c)                                   50. 73 (a)(2)(iv)                 73.71(b)
POWER                         20.405(a)(1 )(i)                       50.36(c)(1)                                 50. 73 (a)(2){v)                 73.71(c) 0%
LEVEL (10)                       20.405(a)(1)(ii)                       50.36(0)(2)                                 50.73(a)(2)(vii)                 OTHER 20.405(a)(1 )(iii)                   )( 50.73(a)(2){i)                               50.73(a)(2)(viii)(A)         (Specify in Abstract below and in Text, NRC 20.405(a)(1)(iv)                       50.73(a) (2) (ii)                           50.73(a)(2){viii)(B)         Form 366A) 20.405(a)(1 )(v)                       50.73(a)(2)(iii)                             50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER (12).
LICENSEE CONTACT FOR THIS LER (12).
J. Pastva, LER Coordinator . i, TELl65'?fE Area code) ... COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TO NPRDS .. SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR .. SUBMISSION I YES . x NO (If yes, complete EXPECTED SUBMISSION DATE) DATE (15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) At 2058 hours on 2/24/95, a dedicated 3rd Nuclear Control Operator (NCO) placed control of pressurizer power relief valve 1PR2 in manual to support removal/inspection and channel calibration of a pressurizer pressure controller.
NA~ichael J. Pastva, LER Coordinator                                                                         . i, TELl65'?fE ~~"g9_:~ 1rg~e Area code)
Effective.the same time, 1PR2 was declared inoperable, in accordance with Technical Specifications (TSs)
COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
* Subsequently, at 2158 hours (same day) the Operations shift did not close the associated block valve, 1PR7, and the 1 hour timeframe of the TS required action was not met. Event discovery was made at 1910 hours on 2/25/95, by the offgoing Operations crew. Immediately following discovery, 1PR7 was closed to terminate the event. The event is attributed to personnel error (inattention to detail) by the involved Operations shift. Contributors:
CAUSE         SYSTEM       COMPONENT       MANUFACTURER       REPORTABLE                                   SYSTEM       COMPONENT       MANUFACTURER       REPORTABLE TONPRDS                         CAUSE                                                            TO NPRDS MONTH              YEAR I  YES SUPPLEMENTAL REPORT EXPECTED (14)
after selecting 1PR2 to manual control the 3rd NCO delayed closing 1PR7; the desk NCO and 3rd NCO became engaged with other work; and open 1PR7 was not recognized during the following shift turnover.
                                                      .                      x
Positive discipline has been taken regarding this event. The Operations Engineer met.with the involved personnel and stressed the need for attention to detail and Management expectations regarding station operation and TS compliance.
                                                                                                              ..                           EXPECTED SUBMISSION DAY (If yes, complete EXPECTED SUBMISSION DATE)                           NO DATE (15)
Nuclear Shift Supervisors have reviewed this event and-lessons learned with their respective shifts. This event will be covered in licensed operator requalification training.  
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
! NRC FORM 366 (5*92)
At 2058 hours on 2/24/95, a dedicated 3rd Nuclear Control Operator (NCO) placed control of pressurizer power relief valve 1PR2 in manual to support removal/inspection and channel calibration of a pressurizer pressure controller. Effective.the same time, 1PR2 was declared inoperable, in accordance with Technical Specifications (TSs)
BLOCK NUMBER 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 ** REQUIRED NUMBER OF DIGITS/CHARACTERS FOR EACH BLOCK NUMBER OF DIGITS/CHARACTERS TITLE UP TO 46 FACILITY NAME 8 TOTAL 3 IN ADDITION TO 05000 DOCKET NUMBER VARIES PAGE NUMBER UP TO 76 TITLE 6TOTAL 2 PER BLOCK EVENT DATE ?TOTAL 2 FORYEAR 3 FOR SEQUENTIAL NUMBER LER NUMBER. 2 FOR REVISION NUMBER 6 TOTAL 2 PER BLOCK REPORT DATE UP TO 18 -FACILITY NAME 8 TOTAL -DOCKET NUMBER OTHER FACILITIES INVOLVED 3 IN ADDITION TO 05000 1 OPERATING MODE 3 POWER LEVEL 1 CHECK BOX THAT APPLIES REQUIREMENTS OF 10 CFR UP TO 50 FOR NAME 14 FOR TELEPHONE LICENSEE CONTACT CAUSE VARIES 2 FOR SYSTEM 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES 1 CHECK BOX THAT APPLIES SUPPLEMENTAL REPORT EXPECTED 6 TOTAL 2 PER BLOCK EXPECTED SUBMISSION DATE . r 
* Subsequently, at 2158 hours (same day) the Operations shift did not close the associated block valve, 1PR7, and the 1 hour timeframe of the TS required action was not met. Event discovery was made at 1910 hours on 2/25/95, by the offgoing Operations crew. Immediately following discovery, 1PR7 was closed to terminate the event. The event is attributed to personnel error (inattention to detail) by the involved Operations shift. Contributors: after selecting 1PR2 to manual control the 3rd NCO delayed closing 1PR7; the desk NCO and 3rd NCO became engaged with other work; and open 1PR7 was not recognized during the following shift turnover. Positive discipline has been taken regarding this event.
., ' 1,., i. 1 * '1*'** I I I. i -*
The Operations Engineer met.with the involved personnel and stressed the need for attention to detail and Management expectations regarding station operation and TS compliance.                                         Nuclear Shift Supervisors have reviewed this event and-lessons learned with their respective shifts.
* LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number LER Number Page 2 of 4 Unit # I 50-272 95-002-00 Plant and System Identification:
This event will be covered in licensed operator requalification training.                                                                                                 !
Westinghouse  
NRC FORM 366 (5*92)
-Pressurized Water Reactor Energy Industry Identification System (EIIS) codes appear in the text as {xx} Identification of Occurrence:
 
                                                                        . r REQUIRED NUMBER OF DIGITS/CHARACTERS FOR EACH BLOCK BLOCK          NUMBER OF TITLE NUMBER    DIGITS/CHARACTERS 1            UP TO 46                 FACILITY NAME 8 TOTAL 2                                      DOCKET NUMBER 3 IN ADDITION TO 05000 3                VARIES                 PAGE NUMBER 4              UP TO 76                 TITLE 6TOTAL 5                                      EVENT DATE 2 PER BLOCK
                  ?TOTAL 2 FORYEAR 6                                      LER NUMBER.
3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 6 TOTAL 7                                      REPORT DATE 2 PER BLOCK UP TO 18 - FACILITY NAME 8                                      OTHER FACILITIES INVOLVED 8 TOTAL - DOCKET NUMBER 3 IN ADDITION TO 05000 9                  1                   OPERATING MODE 10                3                   POWER LEVEL 1
11                                      REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES UP TO 50 FOR NAME 12                                      LICENSEE CONTACT 14 FOR TELEPHONE CAUSE VARIES 2 FOR SYSTEM 13      4 FOR COMPONENT               EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES 1
14                                      SUPPLEMENTAL REPORT EXPECTED CHECK BOX THAT APPLIES 6 TOTAL 15                                      EXPECTED SUBMISSION DATE 2 PER BLOCK
 
Unit # I Salem Generating Station  Docket Number 50-272 LER Number 95-002-00 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Page 2 of 4 Plant and System Identification:
Westinghouse - Pressurized Water Reactor Energy Industry Identification System (EIIS) codes appear in the text as {xx}
Identification of Occurrence:
Failure to Restore Automatic Control Of Pressurizer Power Operated Relief Valve (PORV) 1PR2 Or Close Associated Block Valve 1PR7 Within One Hour Event Date: February 24, 1995 Report Date: March 27, 1995 This report was initiated by Incident Report No. 95-173 Conditions Prior to Occurrence:
Failure to Restore Automatic Control Of Pressurizer Power Operated Relief Valve (PORV) 1PR2 Or Close Associated Block Valve 1PR7 Within One Hour Event Date: February 24, 1995 Report Date: March 27, 1995 This report was initiated by Incident Report No. 95-173 Conditions Prior to Occurrence:
Mode 3 Reactor Power % Unit Load MWe Heatup to normal operating temperature and pressure was in progress.
Mode 3               Reactor Power   %         Unit Load   MWe 1*'**
To assist the Unit console Nuclear Control Operator (NCO) and the desk NCO, a dedicated third NCO was controlling pressurizer pressure, in manual. Description of Occurrence:
Heatup to normal operating temperature and pressure was in progress. To assist the Unit console Nuclear Control I.
  -        Operator (NCO) and the desk NCO, a dedicated third NCO was controlling pressurizer pressure, in manual.
Description of Occurrence:
At 2058 hours on February 24, 1995, the third NCO placed control of PORV 1PR2 in manual to support removal/inspection and channel calibration of pressurizer pressure controller 1PC-455K, in accordance with procedure Sl.IC-CC.RC-0082(Q).
At 2058 hours on February 24, 1995, the third NCO placed control of PORV 1PR2 in manual to support removal/inspection and channel calibration of pressurizer pressure controller 1PC-455K, in accordance with procedure Sl.IC-CC.RC-0082(Q).
Effective the same time, the valve was declared inoperable, in accordance with Technical Specification (TS) 3.4.3, ACTION: a. Subsequently, at 2158 hours (same day) the Operations shift did not close the associated block valve, 1PR7, and therefore the one hour timeframe of the TS required action was not met. Discovery of this occurrence was made at 1910 hours on February 25, 1995, by the offgoing Operations crew, during shift turnover.
Effective the same time, the valve was declared inoperable, in accordance with Technical Specification (TS) 3.4.3, ACTION: a. Subsequently, at 2158 hours (same day) the Operations shift did not close the associated block valve, 1PR7, and therefore the one hour timeframe of the TS required action was not met. Discovery of this occurrence was made at 1910 hours on February 25, 1995, by the offgoing Operations crew, during shift turnover.
Immediately following event discovery, 1PR7 was then closed, which terminated the occurrence.
Immediately following event discovery, 1PR7 was then closed, which terminated the occurrence.
' { *
 
* LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number LER Number Page 3 of 4 Unit # 1 50-272 95-002-00 Analysis of Occurrence:
'{
In MODE 3 (HOT STANDBY), TS 3.4.3, ACTION: a., requires that with one PORV inoperable and capable of being manually cycled, within one hour either restore the PORV to OPERABLE status or close the associated block valve, with power maintained to the block valve; otherwise, be in HOT SHUTDOWN within the following six hours An operable PORV was administratively rendered by placing it in manual control. Subsequently, the TS action time frame to close the associated block valve was not met and the occurrence was not discovered until approximately 22 hours and 12 minutes later. Apparent Cause of Occurrence:
Unit # 1
This occurrence is attributed to "Personnel Error", as classified in NUREG-1022, Appendix B due to inattention to detail by the involved Operations shift crew. When the third NCO selected control of 1PR2 to manual he announced this action to the desk NCO, who logged that the TS action had been entered. However, within the immediate timeframe of placing control of the PORV to manual, the third NCO delayed closing 1PR7. In addition, both NCOs then became engaged with other work in progress and consequently overlooked the required closing of the block valve. Subsequently, the open 1PR7 was not recognized by the involved NCOs and Nuclear Shift Supervisors (NSSs) during the following Operations shift turnover.
* 50-272 LER Number 95-002-00 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number               Page 3 of 4 Analysis of Occurrence:
In MODE 3 (HOT STANDBY), TS 3.4.3, ACTION: a., requires that with one PORV inoperable and capable of being manually cycled, within one hour either restore the PORV to OPERABLE status or close the associated block valve, with power maintained to the block valve; otherwise, be in HOT SHUTDOWN within the following six hours An operable PORV was administratively rendered ~noperable by placing it in manual control. Subsequently, the TS action time frame to close the associated block valve was not met and the occurrence was not discovered until approximately 22 hours and 12 minutes later.
Apparent Cause of Occurrence:
This occurrence is attributed to "Personnel Error", as classified in NUREG-1022, Appendix B due to inattention to detail by the involved Operations shift crew. When the third NCO selected control of 1PR2 to manual he announced this action to the desk NCO, who logged that the TS action had been entered. However, within the immediate timeframe of placing control of the PORV to manual, the third NCO delayed closing 1PR7. In addition, both NCOs then became engaged with other work in progress and consequently overlooked the required closing of the block valve.
Subsequently, the open 1PR7 was not recognized by the involved NCOs and Nuclear Shift Supervisors (NSSs) during the following Operations shift turnover.
Prior Similar Occurrence:
Prior Similar Occurrence:
Review of documentation shows this event is an isolated occurrence.
Review of documentation shows this       event is an isolated occurrence. In this event, the TS       action statement was appropriately entered; however the       required action was not completed within the one hour time       frame, as the result of personnel error.
In this event, the TS action statement was appropriately entered; however the required action was not completed within the one hour time frame, as the result of personnel error. LER 311/94-006-00 reported a Unit 2 occurrence on March 3, 1994, where documented entry into ACTION: ,a of corresponding Unit 2 TS 3.4.5 was not performed following closure of the PORV block valves. In the 1994 occurrence, the TS action statement was not entered due to an interpretive misunderstanding of the action statement.
LER 311/94-006-00 reported a Unit 2 occurrence on March 3, 1994, where documented entry into ACTION: ,a of corresponding Unit 2 TS 3.4.5 was not performed following closure of the PORV block valves. In the 1994 occurrence, the TS action statement was not entered due to an interpretive misunderstanding of the action statement.
'f
 
* LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number LER Number Page 4 of 4 Unit # 1 50-272 95-002-00 Prior Similar Occurrence: (cont'd) Corrective action to the 1994 occurrence included appropriate TS revision.
'f Unit # 1 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number 50-272 LER Number 95-002-00 Page 4 of 4 Prior Similar Occurrence: (cont'd)
Corrective action to the 1994 occurrence included appropriate TS revision.
Safety Significance:
Safety Significance:
This occurrence is reportable pursuant to 10CFR50.73(a)
This occurrence is reportable pursuant to 10CFR50.73(a) (2) (i) (B) due to failure to comply with TS.
(2) (i) (B) due to failure to comply with TS. This occurrence had minimal safety significance as credit is not taken for PORV operation in the accident analyses of the Salem Updated Final Safety Analysis Report. In addition, during this occurrence the PORV remained functionally operable and capable of being opened, if required.
This occurrence had minimal safety significance as credit is not taken for PORV operation in the accident analyses of the Salem Updated Final Safety Analysis Report. In addition, during this occurrence the PORV remained functionally operable and capable of being opened, if required.
Corrective Action: Positive discipline has been taken regarding the personnel error. As a result of this occurrence, the Operations Engineer met with the involved Operations shift personnel and stressed the need for attention to detail and Management expectations regarding operation of the station and TS compliance.
Corrective Action:
Senior Nuclear Shift Supervisors have reviewed the circumstances of this occurrence and lessons learned with their respective shifts. In addition, this occurrence will be covered in licensed operator requalification training.
Positive discipline has been taken regarding the personnel error.
MJPJ:vs REF: SORC Mtg. 95-028 J. C. Summers General Manager -Salem Operations}}
As a result of this occurrence, the Operations Engineer met with the involved Operations shift personnel and stressed the need for attention to detail and Management expectations regarding operation of the station and TS compliance.
Senior Nuclear Shift Supervisors have reviewed the circumstances of this occurrence and lessons learned with their respective shifts.
In addition, this occurrence will be covered in licensed operator requalification training.
J. C. Summers General Manager -
Salem Operations MJPJ:vs REF:     SORC Mtg. 95-028}}

Latest revision as of 05:46, 3 February 2020

LER 95-002-00:on 950224,required TS 1 H Timeframe Not Met Re Closing Associated Block Valve.Caused by Personnel Error. Positive Discipline Has Been taken.W/950327 Ltr
ML18101A605
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/27/1995
From: Pastva M, Summers J
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-95-002-01, LER-95-2-1, NUDOCS 9503310059
Download: ML18101A605 (6)
v • d • e


Text

.,

OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit March 27, 1995 U. s. Nuclear Regulatory Comritission Document Control Desk Washington, DC 20555 Attn: Document Control Desk SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT NO. 95-002-00 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation 10CFR50.73(a) (2) (i) (B). Issuance of this report is required within thirty (30) days of event discovery.

Sincerely, J. C. Summers General Manager -

Salem Operations SORC Mtg.95-028 MJPJ:vs C Distribution LER File 9503310059 950327 PDR ADOCK 05000272 S PDR The po\\*er is in your hands.

95*2168 REV. 6/94

I "NRC 17"0RM 366 5*92)

LICENSEE EVENT REPORT (LER)

. U.S. NUCLEAR REGULATORY COMMISSION ROVED BY OMB NO. 3150-0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.

COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S. NUCLEAR FORWARD REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF (See reverse for required number of digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FAc1urvNAMEt11salem Generating Station - Unit 1 DOCKET NUMBER (2) PAGE (3) 05000 272 1 OF 4 TITLE (4J Failure to Restore Automatic Control of Pressurizer Power Operated Relief Valve (PORV 1PR2 or Close Associated Block Valve 1PR7 Within One Hour -

EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7) OTHER FACILITIES INVOLVED (8)

FACILITY NAME DOCKET NUMBER SEQUENTIAL REVISION DAY YEAR MONTH DAY YEAR YEAR NUMBER NUMBER MONTH 05000 FACILITY NAME .. DOCKET NUMBER 02 24 95 95 -- 002 -- 00 03. 27. 95 05000 OPERATING 3 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR I: .(Check one or more (11)

MODE (9) 20.402(b) 20.405(c) 50. 73 (a)(2)(iv) 73.71(b)

POWER 20.405(a)(1 )(i) 50.36(c)(1) 50. 73 (a)(2){v) 73.71(c) 0%

LEVEL (10) 20.405(a)(1)(ii) 50.36(0)(2) 50.73(a)(2)(vii) OTHER 20.405(a)(1 )(iii) )( 50.73(a)(2){i) 50.73(a)(2)(viii)(A) (Specify in Abstract below and in Text, NRC 20.405(a)(1)(iv) 50.73(a) (2) (ii) 50.73(a)(2){viii)(B) Form 366A) 20.405(a)(1 )(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (12).

NA~ichael J. Pastva, LER Coordinator . i, TELl65'?fE ~~"g9_:~ 1rg~e Area code)

COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS CAUSE TO NPRDS MONTH YEAR I YES SUPPLEMENTAL REPORT EXPECTED (14)

. x

.. EXPECTED SUBMISSION DAY (If yes, complete EXPECTED SUBMISSION DATE) NO DATE (15)

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

At 2058 hours0.0238 days <br />0.572 hours <br />0.0034 weeks <br />7.83069e-4 months <br /> on 2/24/95, a dedicated 3rd Nuclear Control Operator (NCO) placed control of pressurizer power relief valve 1PR2 in manual to support removal/inspection and channel calibration of a pressurizer pressure controller. Effective.the same time, 1PR2 was declared inoperable, in accordance with Technical Specifications (TSs)

  • Subsequently, at 2158 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.21119e-4 months <br /> (same day) the Operations shift did not close the associated block valve, 1PR7, and the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> timeframe of the TS required action was not met. Event discovery was made at 1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br /> on 2/25/95, by the offgoing Operations crew. Immediately following discovery, 1PR7 was closed to terminate the event. The event is attributed to personnel error (inattention to detail) by the involved Operations shift. Contributors: after selecting 1PR2 to manual control the 3rd NCO delayed closing 1PR7; the desk NCO and 3rd NCO became engaged with other work; and open 1PR7 was not recognized during the following shift turnover. Positive discipline has been taken regarding this event.

The Operations Engineer met.with the involved personnel and stressed the need for attention to detail and Management expectations regarding station operation and TS compliance. Nuclear Shift Supervisors have reviewed this event and-lessons learned with their respective shifts.

This event will be covered in licensed operator requalification training.  !

NRC FORM 366 (5*92)

. r REQUIRED NUMBER OF DIGITS/CHARACTERS FOR EACH BLOCK BLOCK NUMBER OF TITLE NUMBER DIGITS/CHARACTERS 1 UP TO 46 FACILITY NAME 8 TOTAL 2 DOCKET NUMBER 3 IN ADDITION TO 05000 3 VARIES PAGE NUMBER 4 UP TO 76 TITLE 6TOTAL 5 EVENT DATE 2 PER BLOCK

?TOTAL 2 FORYEAR 6 LER NUMBER.

3 FOR SEQUENTIAL NUMBER 2 FOR REVISION NUMBER 6 TOTAL 7 REPORT DATE 2 PER BLOCK UP TO 18 - FACILITY NAME 8 OTHER FACILITIES INVOLVED 8 TOTAL - DOCKET NUMBER 3 IN ADDITION TO 05000 9 1 OPERATING MODE 10 3 POWER LEVEL 1

11 REQUIREMENTS OF 10 CFR CHECK BOX THAT APPLIES UP TO 50 FOR NAME 12 LICENSEE CONTACT 14 FOR TELEPHONE CAUSE VARIES 2 FOR SYSTEM 13 4 FOR COMPONENT EACH COMPONENT FAILURE 4 FOR MANUFACTURER NPRDS VARIES 1

14 SUPPLEMENTAL REPORT EXPECTED CHECK BOX THAT APPLIES 6 TOTAL 15 EXPECTED SUBMISSION DATE 2 PER BLOCK

Unit # I Salem Generating Station Docket Number 50-272 LER Number 95-002-00 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Page 2 of 4 Plant and System Identification:

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

Identification of Occurrence:

Failure to Restore Automatic Control Of Pressurizer Power Operated Relief Valve (PORV) 1PR2 Or Close Associated Block Valve 1PR7 Within One Hour Event Date: February 24, 1995 Report Date: March 27, 1995 This report was initiated by Incident Report No.95-173 Conditions Prior to Occurrence:

Mode 3 Reactor Power  % Unit Load MWe 1*'**

Heatup to normal operating temperature and pressure was in progress. To assist the Unit console Nuclear Control I.

- Operator (NCO) and the desk NCO, a dedicated third NCO was controlling pressurizer pressure, in manual.

Description of Occurrence:

At 2058 hours0.0238 days <br />0.572 hours <br />0.0034 weeks <br />7.83069e-4 months <br /> on February 24, 1995, the third NCO placed control of PORV 1PR2 in manual to support removal/inspection and channel calibration of pressurizer pressure controller 1PC-455K, in accordance with procedure Sl.IC-CC.RC-0082(Q).

Effective the same time, the valve was declared inoperable, in accordance with Technical Specification (TS) 3.4.3, ACTION: a. Subsequently, at 2158 hours0.025 days <br />0.599 hours <br />0.00357 weeks <br />8.21119e-4 months <br /> (same day) the Operations shift did not close the associated block valve, 1PR7, and therefore the one hour timeframe of the TS required action was not met. Discovery of this occurrence was made at 1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br /> on February 25, 1995, by the offgoing Operations crew, during shift turnover.

Immediately following event discovery, 1PR7 was then closed, which terminated the occurrence.

'{

Unit # 1

  • 50-272 LER Number 95-002-00 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number Page 3 of 4 Analysis of Occurrence:

In MODE 3 (HOT STANDBY), TS 3.4.3, ACTION: a., requires that with one PORV inoperable and capable of being manually cycled, within one hour either restore the PORV to OPERABLE status or close the associated block valve, with power maintained to the block valve; otherwise, be in HOT SHUTDOWN within the following six hours An operable PORV was administratively rendered ~noperable by placing it in manual control. Subsequently, the TS action time frame to close the associated block valve was not met and the occurrence was not discovered until approximately 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> and 12 minutes later.

Apparent Cause of Occurrence:

This occurrence is attributed to "Personnel Error", as classified in NUREG-1022, Appendix B due to inattention to detail by the involved Operations shift crew. When the third NCO selected control of 1PR2 to manual he announced this action to the desk NCO, who logged that the TS action had been entered. However, within the immediate timeframe of placing control of the PORV to manual, the third NCO delayed closing 1PR7. In addition, both NCOs then became engaged with other work in progress and consequently overlooked the required closing of the block valve.

Subsequently, the open 1PR7 was not recognized by the involved NCOs and Nuclear Shift Supervisors (NSSs) during the following Operations shift turnover.

Prior Similar Occurrence:

Review of documentation shows this event is an isolated occurrence. In this event, the TS action statement was appropriately entered; however the required action was not completed within the one hour time frame, as the result of personnel error.

LER 311/94-006-00 reported a Unit 2 occurrence on March 3, 1994, where documented entry into ACTION: ,a of corresponding Unit 2 TS 3.4.5 was not performed following closure of the PORV block valves. In the 1994 occurrence, the TS action statement was not entered due to an interpretive misunderstanding of the action statement.

'f Unit # 1 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Docket Number 50-272 LER Number 95-002-00 Page 4 of 4 Prior Similar Occurrence: (cont'd)

Corrective action to the 1994 occurrence included appropriate TS revision.

Safety Significance:

This occurrence is reportable pursuant to 10CFR50.73(a) (2) (i) (B) due to failure to comply with TS.

This occurrence had minimal safety significance as credit is not taken for PORV operation in the accident analyses of the Salem Updated Final Safety Analysis Report. In addition, during this occurrence the PORV remained functionally operable and capable of being opened, if required.

Corrective Action:

Positive discipline has been taken regarding the personnel error.

As a result of this occurrence, the Operations Engineer met with the involved Operations shift personnel and stressed the need for attention to detail and Management expectations regarding operation of the station and TS compliance.

Senior Nuclear Shift Supervisors have reviewed the circumstances of this occurrence and lessons learned with their respective shifts.

In addition, this occurrence will be covered in licensed operator requalification training.

J. C. Summers General Manager -

Salem Operations MJPJ:vs REF: SORC Mtg.95-028

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