ML18106A364

LER 98-004-00:on 980204,failure to Comply W/Ts SR 4.1.3.1.1 Was Noted.Caused by Human Error.Review of Both Units 1 & 2 P250 Computer Points Was conducted.W/980306 Ltr

ML18106A364
Person / Time
Site:	Salem
Issue date:	03/06/1998
From:	Bakken A, Bernard Thomas Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-98-004, LER-98-4, LR-N980089, NUDOCS 9803170119
Download: ML18106A364 (6)

Text

e OPS~G Public Servi,ce Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Busi.ness Unit MAR 061998 LR-N980089 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 311/98-004-00 SALEM GENERATING STATION - UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Gentlemen:

This Licensee Event Report entitled "Failure to Comply with Technical Specification Surveillance Requirement 4.1.3.1.1" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50.73(a)(2)(i)(B).

Sincerely, A C. Bakken Ill General Manager -

Salem Operations Attachment I I

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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS. REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED LICENSEE EVENT REPORT (LER) BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC (See reverse for required number of 20555-0001. AND TO THE PAPERWORK REDUCTION PROJECT (3150-01041. OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC digits/characters for each block) 20503.

FACILITY NAME (11 DOCKET NUMBER (2) PAGE (3)

SALEM GENERATING STATION UNIT 2 05000311 1 OFS TITLE (41 Failure to Comply With Technical Specification Surveillance Requirement 4.1 .3.1.1 EVENT DATE 15) LER NUMBER 161 REPORT DATE 171 OTHER FACILITIES INVOLVED 181 MONTH DAY YEAR YEAR I

SEQUENTIAL NUMBER I REVISION NUMBER MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 02 04 98 98 -- 004 -- 00 03 06 98 FACILITY NAME DOCKET NUMBER OPERATING 1 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) 1111 MODE 191 20.2201(b) 20.2203(all2llvl x 50. 73(all2llil 50. 731a112llviiil POWER 100 20.22031all1 I 20.2203(all311il 50. 73(a)(2)(ii) 50. 73(a)(2)(x)

LEVEL 1101 20.2203(a)(2)(i) 20.2203(all311iil 50. 73(a)(2)(iii) 73.71 20.2203(all211iil 20.2203(a)(4) 50. 731all211ivl OTHER 20.2203(all211iiil 50.361cll 1I 50. 731all2llvl Specify in Abstract below or in NRC Form 366A 20.2203(a)(2)(ivl 50.361cll21 50. 73(a)(2)(viil LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER (Include Area Codel Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPROS IYES SUPPLEMENTAL REPORT EXPECTED 1141 (If yes. complete EXPECTED SUBMISSION DATE).

I XINO EXPECTED SUBMISSION DATE(15)

MONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) 1161 At 1620 on February 4, 1998, the Rod Position Deviation Monitor was declared inoperable when it was determined that the Plant Processing Computer System (P250) was not updating the Rod Position Deviation computer data point "RODDEV". The "RODDEV' computer data point is the Rod Position Deviation Monitor credited in Technical Specification (TS) Surveillance Requirement 4.1.3.1.1. On November 21, 1997, computer point "RODDEV" was disabled apparently without informing the Control Room personnel. Since the operators were not aware that the Rod Position Deviation Monitor was inoperable, control rod positions were not verified every four hours as required TS surveillance requirement 4.1.3.1.1.

The apparent cause of this event is attributed to human error. Corrective actions associated with this event consisted of a lesson learned discussion and the implementation of periodic reviews of the P250 computer points to ensure Technical Specification associated points are not disabled.

This event is being reported in accordance with 10 CFR 50. 73(a)(2)(i)(B), any condition prohibited by the plant's Technical Specifications.

NRC FORM 366 (4-95)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (11 DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SALEM GENERATING STATION UNIT 2 05000311 YEAR I SEQUENTIAL NUMBER I REVISION NUMBBI 2 0F 5 98 - 004 - 00 TEXT (If more space is required. use additional copies of NRC Form 366Al (171 PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Plant Computer (COM) {ID/-}*

Rod Control System (RCS) {JD/-}

• Energy Industry Identification System (EllS) codes and component function identifier codes appear as {SS/CCC}.

CONDITIONS PRIOR TO OCCURRENCE At the time of occurrence, Salem Unit 2 was in Mode 1 at 100% Power.

DESCRIPTION OF OCCURRENCE At 1620 on February 4, 1998, the Rod Position Deviation Monitor was declared inoperable when it was determined that the Plant Processing Computer System (P250) was not updating the Rod Position Deviation computer data point "RODDEV'. The "RODDEV" data point provides the input to Overhead Alarm (OHA) window E-24 ("ROD DEV OR SEQ") which automatically alarms when the rods deviate beyond the required number of steps from the group demand counter. The "RODDEV" computer data point is the Rod Position Deviation Monitor credited in Technical Specification (TS)

Surveillance Requirement 4.1.3.1.1.

TS Surveillance Requirement 4.1.3.1.1 states that:

"The position of each full length rod shall be determined to be within the limits established in the limiting condition for operation at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (allowing for one hour thermal soak after rod motion) except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />."

NRC FORM 366A (4-95)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER (61 PAGE (31 SALEM GENERATING STATION UNIT 2 05000311 VEAR I SEQUENTIAL NUMBER I REVlSION NUMBER 3 OF 5 98 - 004 - 00 TEXT (If more space is required, use additional copies of NRC Form 366AI ( 171 DESCRIPTION OF OCCURRENCE (cont'd)

A review of computer historical data revealed that computer point "RODDEV" was disabled on November 21, 1997. A Digital Systems Group engineer working in the Unit 2 Control Room Computer Room disabled the "RODDEV' computer point to avoid expected nuisance alarms of OHA window E-24 during work on the P250 computer not related to the Rod Position Deviation Monitor.

Control Room personnel were apparently not informed of this action. The computer point was inadvertently left disabled when work in the Computer Room was completed. Since the operators were not aware that the Rod Position Deviation Monitor was inoperable, control rod position verification was not performed every four hours during the period between December 8, 1997 and February 4, 1998, as required by TS surveillance requirement 4.1.3.1.1 to perform the control rod position verification every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Prior to December 8, 1997, supplemental control rod position verification was being performed at four hour intervals to comply with TS Surveillance Requirement 4.1.3.5 due to the Rod Insertion Limit Monitor being out of service.

The discovery of this event was delayed due to an inadequate process for performing periodic checks of P-250 computer point status. Upon discovery of the inoperable Rod Position Deviation Monitor, increased control rod position verification in accordance with TS Surveillance Requirement 4.1.3.1.1 was commenced. Computer point "RODD EV' was returned to service and OHA window E-24 was verified operable by satisfactory completion of functional testing. The increased control rod position verification was discontinued at 1632 on February 4, 1998.

CAUSE OF OCCURRENCE The apparent cause of this event is attributed to human error. A Digital Systems Group engineer working in the Unit 2 Control Room Computer Room disabled the "RODDEV" computer point to avoid expected nuisance alarms of OHA window E-24 during work on the P250 computer not related to the Rod Position Deviation Monitor without apparently informing Control Room personnel. The computer point was inadvertently left disabled when work in the Computer Room was completed.

A contributing cause of this event was inadequate tracking of P250 computer configuration control.

No process existed to administratively track computer points that are disabled by conducting periodic checks of P250 computer point status. Additionally, Control Room logs that implement TS Surveillance Requirement 4.1.3.1.1 do not verify the operability of the P250 computer point.

NRC FORM 366A (4-95)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER 121 LER NUMBER (6) PAGE (3)

SALEM GENERATING STATION UNIT 2 05000311 YEAR I SEQUENTIAL NUMBER I REVISION NUMBBI 4 OF 5 98 - 004 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) ( 1 7 I PRIOR SIMILAR OCCURRENCES A review of LERs issued in the past two years did not identify any prior similar occurrences.

SAFETY CONSEQUENCES AND IMPLICATIONS Control Room operators were verifying individual control rod positions every four hours from November 21, 1997 through December 8, 1997 in accordance with TS 4.1.3.5 due to the Rod Insertion Limit Monitor being out of service. Although the shorter time interval of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for verification of control rod position was not being met as required by TS 4.1.3.1.1 due to the inoperable Rod Position Deviation Monitor, rod position verification was being performed at least every twelve hours in accordance with TS 4.1.3.1.1. A review of the completed control room logs since November 21, 1997 revealed that control rods remained within the requirements of the Limiting Condition for Operation 3.1.3.1 throughout the period. Therefore, the health and safety of the public were not affected.

CORRECTIVE ACTIONS

1. P250 computer point "RODDEV" was returned to service and OHA window E-24 was verified operable by satisfactory completion of a functional test on February 4, 1998.

2. A review of both Unit 1 and 2 P250 computer points was conducted. No other computer points supporting Technical Specification requirements were identified as being disabled.

3. Lessons learned from this event were discussed with Digital System Group personnel. An administrative procedure is also being developed for the control of activities associated with the P250 computer. This procedure will be developed by June 30, 1998.

Additionally, personnel involved in this event would have been held accountable for their inappropriate actions in accordance with PSE&G procedures, however, the individual involved in this event left PSE&G prior to the occurrence of this event.

4. A weekly review of both Units' P-250 computers for disabled computer points has been implemented. Computer points that are identified as being disabled will then be tracked in accordance with procedure SC.OP-DL.ZZ-0010(0), "Control Room Instrumentation and Alarms".

NRC FORM 366A (4-95)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION (4-95)

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (11 DOCKET NUMBER (2) LER NUMBER 161 PAGE (3)

SALEM GENERATING STATION UNIT 2 05000311 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 5 OF 5 98 - 004 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) 117 I CORRECTIVE ACTIONS (cont'd)

5. As an additional enhancement to further ensure compliance with Technical Specifications, procedures S1/S2.0P-DL.ZZ-0003(Q), "Control Room Readings," will be revised to verify P250 computer operability. These procedureswill be revised by May 13, 1998.

6. Additional controls will be implemented to ensure that control room personnel are notified when computer points are put in an off-normal state, and verification is performed when the computer points are returned to operable status. These controls will be implemented by June 30, 1998.

7. A weekly surveillance test will be developed to verify the inputs for key computer points. This surveillance test will be issued by June 1, 1998.

NRC FORM 366A (4-95)