ML18102A686

LER 96-033-00:on 961118,inadequate Sample Purge Times Resulted in Inadequate TS Surveillances.Caused by Less than Adequate Review & Implementation of Sample Purge Times. Chemistry Procedures reviewed.W/961217 Ltr

ML18102A686
Person / Time
Site:	Salem
Issue date:	12/17/1996
From:	Garchow D, Hassler D Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-96-033, LER-96-33, LR-N96417, NUDOCS 9612260075
Download: ML18102A686 (4)

Text

e OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit DEC 171996 LR-N96417 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 LER 272/96-033-00 SALEM GENERATING S.TATION - UNIT 1 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Gentlemen:

This Licensee Event Report entitled "Inadequate Sample Purge Times Results In Inadequate Technical Specifictaions Surveillances" is being submitted pursuant to the requirements of the Code of Federal Regulations 10CFR50. 73 (a) (2) (i) (B).

Sincerely, ;J

~J..OV\,t Q.Q f F:~:rchow David General Manager -

Salem Operations Attachment SORC Mtg. 96-1417 DVH c Distribution LER File 3.7 9612260075 961217 PDR ADOCK 05000272 S PDR The power is in your hands.

95-2168 REV. 6/94

NRCFORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMO 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 LICENSEE EVENT REPORT (LER) LICENSING PROCESS AND FED BACK TO INDUSTRY. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T~ F33J, U.S. NUCLEAR (See reverse for required number of REGULATORY COMMISSION, ',,,SHINGTON, DC 20 55-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF digits/characters for each block) MANAGEMENT AND BUDGET, WASHINGTON, DC 20503 .

FACILITY NAllE (1) uuo:;KET NUllBER (2) PAGE (3)

SALEM GENERATING STATION UNIT 1 05000272 1 OF 3 TITLE (4)

INADEQUATE SAMPLE PURGE TIMES RESULTS IN INADEQUATE TECHNICAL SPECIFICATIONS SURVEILLANCES EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR I SEQUENTIAL NUMBER IREVISION NUMBER MONTH DAY YEAR FACILITY NAME Salem Unit 2 DOCKET NUMBER 05000311 FACILITY NAME DOCKET NUMBER 11 18 96 96 - 033 - 00 12 17 96 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 000 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 I-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)

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 CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR SUBMISSlm~

IYES

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

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

After a review of INPO Significant Event Notice 139, Chemistry determined there were samples being obtained for Technical Specification surveillances that did not have purge times to ensure representative samples were obtained. These samples were performed with less than one sample line volume flushed prior to obtaining the sample. The determination is that these samples were not representative and could not be used to satisfy the Technical Specification Surveillances requirements. The sarrples involved were for surveillances required in Mode 6 for Reactor Coolant System boron concentration and for surveillances required at all times for Fluoride and Chloride content in the Reactor Coolant System.

The cause of this occurrence is less than adequate review and irrplementation of sampling purge times to ensure that representative samples were obtained. Corrective actions include a review of Chemistry procedures currently in use to ensure representative samples are obtained and completion of a root cause evaluation.

This event is reportable in accordance with 10 CFR 73 (a) (2) (i); 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 05 0002 72

• YEAR I' ..:iC'..:wC:NTIAl..

NUMBER I R£"~*;s1c.;N NUMBER 2 OF 3 SALEM GENERATING STATION UNIT 1 96 - 033 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

PLANT AND SYSTEM IDENTIFICATION Westinghouse - Pressurized Water Reactor Reactor Coolant System {AB/-}*

• 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 INPO Significant Event Notification (SEN) 139, Recurring Event, Inadequate Sampling and Calculations Cause 180 ppm Boron Dilution, identified that inadequate purge times during sampling can result in non-representative samples.

After a review of SEN-139, Chemistry determined there were samples being obtained for Technical Specification surveillances that were performed with less than an adequate sample line volume flush prior to obtaining the sample.

Reactor Coolant System (RCS) samples obtained in Mode 6 to meet Technical Specification Surveillance 4.9.1, Refueling Operations, for boron concentration used the Chemical Volume and Control System (CVCS) Demineralizer Inlet sample point. These samples were obtained July 25, 1995 to August 5, 1995 in Salem Unit 1 at which time Unit 1 entered Mode Undefined. Similar samples were obtained from December 15 to 18, 1995 in Salem Unit 2 at which time Unit 2 entered Mode Undefined. These samples did not have purge times sufficient for an adequate line volume flush prior to obtaining the sample. Therefore, these were not representative samples and could not be used to satisfy the Technical Specification surveillance requirement.

RCS sa1nples obtained in l'-'1cde 5 t:.o . -:-.ee~ .::.:.:..--=. .. :. :.. .. -...~.'c : ~*echr:.:.::al Spec.:i...:ica.tio:--..

• Surveillance 4.4.7 (4.4.8 for Unit 2) for RCS and Fluoride and Chloride also were obtained using the eves Demineralizer Inlet sample point. These samples were obtained July 25, 1995 to August 5, 1995 in Salem Unit 1, December 15 to 18, 1995 in Salem Unit 2, and routinely from August 8, 1995 to October 25, 1995 in Salem Unit 2.

These samples also did not have purge times for an adequate line volume flush prior to obtaining the sample. Therefore, these were not representative samples and could not be used to satisfy the Technical Specification surveillance requirement.

Salem Unit 1 Technical Specification 3.7.8 (3.7.8 for Unit 2) and associated surveillances were deleted from the Salem Technical Specifications in February 1996.

____ .:.;;.;._.:...=:*-*---=----::::.=-:*_..:;... ----_ _-::=:. - .

NRC FORM 366.A (4-95)

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

LICENSEE EVENT REPORT (LER)

TEXT CONTINUATION FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SALEM GENERATING STATION UNIT 1 96 - 033 - 00 TEXT (If more space is required, use additional copies of NRC Form 366A) (17)

CAUSE OF OCCURRENCE The cause of this occurrence is less than adequate review and implementation of sampling purge times to ensure that representative samples were obtained for Technical Specification surveillances.

PRIOR SIMILAR OCCURRENCES In the past two years there were four LERs that addressed Chemistry sampling issues.

These LERs are 272/96-003, 311/95-005, 311/96-001, and 311/96-011. However, none of the LERs addressed inadequate sampling due to sample purge times.

SAFETY CONSEQUENCES AND IMPLICATIONS Monitoring the boron concentration of primary samples is significant in regards to nuclear safety. Boron is used for reactivity control of the reactor coolant system.

During Mode 6 operation, the minimum concentration of boron ensures that the reactor will remain subcritical during core alterations. Although samples were not fully representative, a review of the data, system characteristics and sampling protocol provides reasonable assurance that the RCS was maintained within Technical Specification limits.

Not accurately monitoring the chloride and fluoride concentrations of the RCS is potentially significant in regards to both the nuclear and radiological safety. The purpose of this surveillance is to ensure the corrosion potential of the reactor coolant is maintained at a minimal level. The results of this samples were less than 33% of the Technical Specification limit. Although samples were not fully representative, a review of the data, system characteristics and sampling protocol provides reasonable assurance that the RCS was maintained within Technical Specification limits.

There were no safety consequences associated with this occurrence. The health and safety of the public were not affected.

CORRECTIVE ACTIONS

1. Chemistry procedures currently being used have been reviewed to ensure that representative samples are obtained to satisfy Technical Specification requirements.

2. A root cause evaluation will be completed by December 18, 1996 which will document the review of sampling points required for Technical Specification compliance. The root cause will also identify non Technical Specification sample points that require further evaluation.

NRC FORM 366A (4-95)