ML18102A271

LER 96-005-00:on 960627,surveillance of Fuel Handling Bldg Ventilation Sys Charcoal Adsorber Test Was Missed.Caused by Inattention to Detail.Individual Involved Received Appropriate Level of Positive discipline.W/960726 Ltr

ML18102A271
Person / Time
Site:	Salem
Issue date:	07/26/1996
From:	GARCHOW D F, HASSLER D V Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-96-005-02, LER-96-5-2, LR-N96210, NUDOCS 9608010262
Download: ML18102A271 (5)

Text

e Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit JUL 2 6 1996 LR-N96210 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

LER 311/96*-005-00 SALEM GENERATING STATION -UNIT 2 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 This Licensee Event Report entitled "Missed Surveillance of Fuel Handling Building Ventilation System Charcoal Adsorber Test" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B). Attachment SORC Mtg.96-101 DVH/tcp c Distribution LER File 3.7 9608010262 960726 PDR ADOCK 05000311 S PDR The F()\\tT is in \*our hands.

David F. General Manager -Salem Operations 010071 95-2168 REV. 6/94 Document Control Desk LR-N96210 Attachment A JUL 2 6 7996 The following item represents the commitments that Public Service Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission (NRC) relative to this LER (311/96-005-00).

The commitments are as follows: 1. The responsible individual will receive the appropriate level of positive discipline in accordance with the Public Service Electric & Gas Positive Discipline Program by August 1, 1996. 2. This LER will be reviewed with all Radiation Protection personnel.

This will be completed by 8/15/96.

' w NRCFORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (4-95) EXPIRES 04/30198 EmllATEO BURDEN PER RESPONSE TO COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: llO.O HRS. LICENSEE EVENT REPORT (LER) REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE UC ENSING PROCESS AND FED BACK TO INDUSTR'f'.

FORWARD COMMENTS REGARDING BURDEN EmllATE TO THE INFORMATION (See reverse for required number of AND RECORDS MANAGEMENT BRANCH (T _.

REGULATORY COMMISSION WASHINGTON, DC , AND TO digits/characters for each block) THE PAPERWORK REDUCTION PROJECT OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, 20603. FACILITY NAllE (1) DOCKET NUllBER (2) PAOE(3) SALEM GENERATING STATION, UNIT 2 05000311 1 OF3 TITLE(4) Missed Surveillance of Fuel Adsorber Test Handling Building Ventilation System Charcoal EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILmES INVOLVED (8) YEAR I FACILITY NAllE DOCKET NUllBER MONTH DAY YEAR SEQUENTIAL

'REVISION MONTH DAY YEAR NUMBER NUMBER 05000 06 27 96 96 005 00 07 26 96 FACILITY NAME DOCKET NUMBER --05000 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)

Abetnlct below 20.2203(a)(2)(iv) 50.36(c)(2)

50. 73(a)(2)(vii) or In C Form 388A LICENSEE CONTACT FOR THIS LER (12) NAME TELEPHONE NUMBER (Include Ana Coda) Dennis v. Hassler, LER Coordinator 609-339-1989 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE II CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TONPRDS TONPRDS 111111111111 SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR IYES XINO SUBMISSION (If yea, complete EXPECTED SUBMISSION DATE). DATE(15) ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) On June 27, 1996 a review of charcoal adsorber test records identified an occurrence where a Salem Unit 2 Fuel Handling Building (FHB) charcoal Adsorber sample was tested in October 1995 to Salem Unit 1 acceptance criteria.

The Unit 2 acceptance criteria is different than the Unit 1 acceptance criteria.

The Unit 2 charcoal adsorber test was performed in October 1995 as part of the 18 month Technical Specifications Surveillance for the FHB Ventilation System. Because the incorrect acceptance criteria was used to determine charcoal filter efficiency, the result constituted a missed/inadequate Technical Specifications Surveillance.

The cause of this occurrence is a human error caused by inattention to detail and failure to use the STAR (Stop, Think, Act, Review) techniques.

The responsible individual will receive the appropriate level of positive discipline in accordance.with the Public Service Electric & Gas Positive Discipline Program by August 1, 1996. This event is reportable in accordance with 10 CFR 73(a) (2) (i) (B) ' any condition prohibited by the plant's Technical Specifications.

NRC FORM 386 (4-95)

NRC FORM 366A (4-95) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER 8) PAGE {3} 05000311 YEAR I 2 OF 3 SALEM GENERATING STATION, UNIT 2 96 -005 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) PLANT AND SYSTEM IDENTIFICATION Westinghouse

-Pressurized Water Reactor Fuel Handling Building Ventilation System {VG/-}*

• Energy Industry Identification System (EIIS) codes and component function identifier codes appear as (SS/CCC) CONDITIONS PRIOR TO OCCURRENCE At the time of identification, Salem Units 1 and 2 were shutdown and defueled.

DESCRIPTION OF OCCURRENCE On June 27, 1996 a review of charcoal adsorber test records identified an occurrence where a Salem Unit 2 Fuel Handling Building (FHB) Ventilation System {VG/-} charcoal adsorber sample was tested in October 1995 to Salem Unit 1 acceptance criteria.

The Unit 2 Technical Specifications reference Regulatory Guide 1.52 for the acceptance criteria which are a loading temperature of 80 degrees Celsius and an iodine removal efficiency of greater than or equal to 99 percent. The Unit 1 acceptance criteria are stated in the Technical Specifications and are 130 degree Celsius for the loading temperature_

and greater than or equal to 90 percent efficiency for removal of. iodine. The Unit 2 adsorber test was performed in October 1995 as part of the 18 month Technical Specifications Surveillance for the FHB Ventilati_on System. The individual responsible for specifying the test criteria to be used by the vendor in performing the charcoal adsorber_

test had recently been assigned this responsibility.

The individual was not aware that the Salem Unit 1 and 2 charcoal adsorber test requirements were different.

The individual used a previous Unit 1 charcoal adsorber test as an example and did not verify that the correct criteria, as stated in the procedure, was being specified.

Because the incorrect acceptance criteria was used to determine charcoal filter efficiency, the result constituted a missed/inadequate Technical Specifications Surveillance.

The last valid FHB surveillance was performed in July 1994, therefore the 18 month time period including a 25 percent extension was exceeded starting in mid May 1996. A Unit 2 FHB charcoal adsorber sample was collected and sent to the vendor for testing. At the same time the FHB Ventilation system was .declared inoperable.

The results of the test performed on June 28, 1996 met the acceptance criteria and the FHB ventilation was again declared operable.

In the period from June 12, 1996 through June 15, 1996 there was fuel movement within the spent fuel pool in order to perform ultrasonic testing of fuel assemblies.

NRC FORM 366A (4-95)

NRC FORM 388A (4-95) FACILITY NAME (1) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION DOCKET NUMBER (2) LER NUMBER 8) PAGE (3) 05000311 YEAR I SE.fill.fr.IkAL 3 OF 3 SALEM GENERATING STATION, UNIT 2 96 -005 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17) CAUSE OF OCCURRENCE The cause of this occurrence is a human error caused by inattention to detail and failure to use the STAR (Stop, Think, Act, Review) techniques.

PRIOR SIMILAR OCCURRENCES During the past two years there were no LERs involving Technical Specification Surveillances being performed using the incorrect acceptance criteria.

However, there were two LERs that addressed ventilation testing. LER 311/95-006-00 addressed a missed surveillance for the Control Room Emergency Air Conditioning System. In this LER the surveillance exceeded the requirement to sample the charcoal adsorber after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of cumulative operation.

The cause of this occurrence was the failure to adequately track the hours of cumulative operation.

LER 272/96-005-02 addressed an inadequacy in the bypass testing of the Auxiliary Building and FHB ventilation systems. The bypass flow leakage through the normal filtration unit was not adequately measured.

The cause of this occurrence was the lack of adequate controls and understanding of the development and maintenance of Technical Specifications surveillance procedures.

SAFETY CONSEQUENCES AND IMPLICATIONS The charcoal Adsorber was tested on June 28, with acceptable test results. Based on the acceptable results, it is reasonable to conclude that the charcoal adsorbers would in the past have performed their intended function.

Therefore, there were no safety consequences associated with this event. The implication of this missed surveillance is, had the retest results been unsatisfactory, the Fuel Handling Building ventilation system may not have performed its design basis function.

The public health and safety was not affected py this occurrence.

CORRECTIVE ACTIONS 1. The responsible individual will receive the appropriate level of positive discipline in accordance with the Public Service Electric & Gas Positive Discipline Program by August 1, 1996. 2. This LER will be reviewed with all Radiation Protection personnel.

This will be completed by 8/15/96. NRC FORM 366A (4-95)