ML18102B475

LER 97-007-00:on 970630,failure to Perform Independent Verification for Radioactive Release Lineup as Required by TS 3.3.3.8,noted.Caused by Personnel Error.Cr Supervisor Was Held Accountable for actions.W/970729 Ltr

ML18102B475
Person / Time
Site:	Salem
Issue date:	07/29/1997
From:	Garchow D, Bernard Thomas Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-97-007-02, LER-97-7-2, LR-N970464, NUDOCS 9708060039
Download: ML18102B475 (5)

Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236

, Nuclear Business Unit JUL 2 9 1997 LR-N970464 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

LER 272/97-007-00 SALEM GENERATING STATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 This Licensee Event Report entitled "Failure to Perform Independent Verification of Radioactive Release Lineup Required by Technical Specification 3.3.3.8," is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B).

.a;;y, David F. ~

General Manager -

Salem Operations Attachment BJT C Distribution LER File 3.7 9708060039 970729 PDR ADOCK 05000272 S PDR Illllll lllll lllll lllll lllll lllll llll llll

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The power is in your hands.

95-2168 REV. 6/94

.... NRC FORM 366 (4-95)

LICENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPIRES 04130198 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 BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T~ F33), U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, WASHINGTON, DC 20555--0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150--0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

FACILITY NAllE (1) DOCKET NUllBER (2) PAGE (3)

SALEM GENERATING STATION, UNIT 1 05000272 1 OF4 TITLE (4)

Failure to Perform Independent Verification for Radioactive Release Lineup Required by Technical Specification 3. 3. 3. 8 EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL IREVISION MONTH DAY YEAR FACILITY NAME DOCKET NUMBER I NUMBER NUMBER 06 30 97 97 -- 007 -- 00 07 29 97 FACILITY NAME DOCKET NUMBER OPERATING N THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more) (11)

MODE(9) 20.2201(b) 20.2203(a)(2)(v) x 50. 73(a)(2)(i) 50. 73(a)(2)(viii)

POWER 0 20.2203(a)(1) 20.2203(a)(3)(i) 50. 73(a)(2)(ii) 50. 73(a)(2)(x)

LEVEL (10) 20.2203(a)(2)(i) 20.2203(a)(3)(ii) 50. 73(a)(2)(iii) 73.71 20.2203(a)(2)(ii) 20.2203(a)(4) 50. 73(a)(2)(iv) OTHER 20.2203(a)(2)(iii) 50.36(c)(1) 50. 73(a)(2)(v) Spec~in Abstract below or in C Form 366A 20.2203(a)(2)(iv) 50.36(c)(2) 50. 73(a)(2)(vii)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER (Include Area Code)

Brian J. Thomas, Licensing Engineer 609-339-2022 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

I CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TO NPRDS 11111111111111111111111111111 SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR SUBMISSION

'YES (If yes, complete EXPECTED SUBMISSION DATE). XINO DATE (15)

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

On 6/30/97, radioactive liquid waste was released from the 11 Chemical and Volume Control System Monitoring Tank without performing an independent verification for a portion of the discharge line valving as required by Technical Specification 3. 3. 3. 8. The independent verification was required since the Waste Disposal System Liquid Effluent Radiation Monitor (1R18) was inoperable.

The Control Room Supervisor (CRS) inadvertently marked a procedure step requiring independent verification of a portion of the discharge lineup as "NI A" and as a result the required independent verification was not performed. The root cause of this event was personnel error as a result of inattention to detail and lack of self verification by the CRS. The CRS was held accountable for his actions and the Operations Manager will conduct detailed discussions of this event with the operating crews during Licensed Operator training, emphasizing Management expectations on the use of self-verification and minimization of distractions.

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 (4-95)

• LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000272 .

YEAR I SEQUENTIAL NUMBER IREVISION NUMBER 2 OF 4 SALEM GENERATING STATION, UNIT 1 97 -- 007 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Liquid Waste System (LWS) {WD/-}*

Chemical and Volume Control System (CVCS) {CB/-}*

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

CONDITIONS PRIOR TO OCCURRENCE At the time of occurrence Salem Unit 1 was defueled.

DESCRIPTION OF OCCURRENCE At 0011, on 6/30/97, the radioactive liquid waste contents of the 11 Chemical and Volume Control System (CVCS) Monitor Tank {CB/TK} were released without performing an independent verification for a portion of the discharge lineup as required by Technical Specification 3.3.3.8. The independent verification was required since the Waste Disposal System Liquid Effluent Radiation Monitor (1R18) was inoperable. Radiation Monitor 1R18 was taken out of service in February 1996 to support design modification work associated with the replacement of Radiation Monitor lRlB during the Control Room Ventilation modification. Radiation Monitor 1R18 is currently out of service to support inspection and replacement of capacitors, implementation of a modification to change the setpoint, and required Technical Specification testing.

The failure to perform the independent verification was identified immediately following completion of the 'release at 0336 on 6/30/97.

Technical Specification Table 3.3-12, Action 26 requires the following actions to be taken if radiation monitor 1R18 is inoperable:

"With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway."

Two independent samples were analyzed and release rate calculations were independently verified prior to the release from the 11 eves Monitoring Tank; however, contrary to the requirements of Action 26, an independent verification was not performed for a portion of the discharge line valving.

NRC FORM 366A (4-95)

\

1.

NRC FORM 366A (4-95)

• LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000272 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 3 OF 4 SALEM GENERATING STATION, UNIT 1 97 -- 007 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

DESCRIPTION OF OCCURRENCE (cont'd)

During the review of the procedure to perform the radioactive liquid release, the Control Room Supervisor (CRS) inappropriately marked a step in the procedure "N/A". This step in the procedure directed the performance of the independent verification for a portion of the liquid release pathway. The CRS allowed himself to become distracted with other evolutions and priorities while performing the review of the liquid waste discharge procedure. This, coupled with the failure to use proper self-verification techniques, led to the inappropriate action by the CRS.

CAUSE OF OCCURRENCE The root cause of this event was personnel error as a result of inattention to detail and a lack of self-verification by the CRS.

PRIOR SIMILAR OCCURRENCES A review of LERs for Salem Units 1 and 2 for the past two years identified two prior similar occurrences.

LER 311/95-005-00, "Failure to analyze second sample with Radiation Monitor Inoperable," describes an event where liquid was released from the 22 eves Monitor Tank with the 2R18 radiation monitor inoperable. This event involved a failure by chemistry personnel to analyze and compare the spectra of the two independent samples prior to authorizing the release as required by Technical Specifications. Corrective actions included adding specific verification signature requirements for the analysis of independent samples to the gaseous and liquid waste release procedures.

LER 272/96-006-00, "Missed independent.verification of release lineup on Waste Gas Decay Tanks," identifies 11 releases from the Unit 2 Waste Gas Decay Tanks with the 2R41C monitor inoperable. The required independent verification of the discharge valve lineup required by Technical Specifications was not performed because a step had been inappropriately removed from the procedure. Corrective actions included a review of the liquid waste discharge procedures which determined that appropriate independent verification requirements for conditions when the associated radiation monitors are out of service were included in the procedure.

NRC FORM 366A (4*95)

NRC FORM 366A (4-95)

• LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION U.S. NUCLEAR REGULATORY COMMISSION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) 05000272 YEAR I SEQUENTIAL NUMBER I REVISION NUMBER 4 OF 4 SALEM GENERATING STATION, UNIT 1 97 -- 007 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

SAFETY CONSEQUENCES AND IMPLICATIONS Failure to perform an independent verification of the lineup could potentially result in release of radioactive liquids to and from unwanted locations.

However, there were no actual safety consequences associated with this event since the restoration lineup confirmed that the release flowpath and the correct eves Monitor tank were properly aligned for the liquid waste discharge. A chemical analysis was performed and independently verified prior to the release which confirmed that the radioactivity in the 11 eves Monitoring Tank was well within release limits. Therefore, there was no impact to the health and* safety of the public.

CORRECTIVE ACTIONS

1. The Control Room Supervisor was held accountable for his actions in accordance with PSE&G's disciplinary policies.

2. The Operations Manager will conduct detailed discussions of this event with the operating crews during Licensed Operator training, emphasizing Management expectations on the use of self-verification and minimization of distractions.

3. Although the procedure provided the necessary steps for performance of the independent verification, the procedures for radioactive waste discharges will be evaluated for human factors enhancements. Any identified enhancements will be incorporated by October 31, 1997.

4. Radiation Monitor 1R18 is expected to be returned to service in mid-August following implementation of a modification to change the setpoint, inspection and replacement of capacitors, and required Technical Specification testing.

NRC FORM 366A (4-95)