ML18100A877: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 20: Line 20:


==Dear Sir:==
==Dear Sir:==
SALEM GENERATING STATION LICENSE NO. DPR.,..70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 94-001-00 February 3, 1994 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation lOCFR50.73(a)  
SALEM GENERATING STATION LICENSE NO. DPR.,..70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 94-001-00 February 3, 1994 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation lOCFR50.73(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.
MJPJ:pc Distribution 940203 S ADOCK 05000272 PDR Sincerely yours, //;* £//  
MJPJ:pc Distribution 940203 S ADOCK 05000272 PDR Sincerely yours, //;* £//
: c. A. Vondra General Manager -' Salem Operations rc"LL I I I 95-2189 REV 7-92   
: c. A. Vondra General Manager -' Salem Operations rc"LL I I I 95-2189 REV 7-92   
------------------
------------------
NRC FOJ3M 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 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 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. FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3) Salem Generating Station -Unit 1 05000 272 1 OF04 TITLE (4) TS 3.0.3 Entries; More Than One Inoperable ARPI Per Bank. EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7l OTHER FACILITIES INVOLVED (8) SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR 05000 311 NUMBER Salem Unit 2 FACILITY NAME DOCKET NUMBER 01 05 94 94 --001 --00 02 94 05000 03 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more (11 l MODE (9) 2 20.402(b) 20,405(c)  
NRC FOJ3M 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 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 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. FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3) Salem Generating Station -Unit 1 05000 272 1 OF04 TITLE (4) TS 3.0.3 Entries; More Than One Inoperable ARPI Per Bank. EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7l OTHER FACILITIES INVOLVED (8) SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR 05000 311 NUMBER Salem Unit 2 FACILITY NAME DOCKET NUMBER 01 05 94 94 --001 --00 02 94 05000 03 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more (11 l MODE (9) 2 20.402(b) 20,405(c)
: 50. 73(a)(2)(iv) 73.71(b) POWEI=l 20.405(a)(1  
: 50. 73(a)(2)(iv) 73.71(b) POWEI=l 20.405(a)(1  
)(i) 50.36(c) (1) 50. 73(a)(2)(v) 73.71 (c) LEVEL (10) 000 20.405(a)  
)(i) 50.36(c) (1) 50. 73(a)(2)(v) 73.71 (c) LEVEL (10) 000 20.405(a)
(1) (ii) 50.36(c) (2) 50.73(a)(2)(vii)
(1) (ii) 50.36(c) (2) 50.73(a)(2)(vii)
OTHER .
OTHER .
20.405(a)  
20.405(a)
(1) (iii) x 50.73(a)(2)(i)  
(1) (iii) x 50.73(a)(2)(i)
: 50. 73(a)(2)(viii)(A) (Specify in Abstract 20.405(a)  
: 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 Tex1, NRG Form 366A) 20.405(a)(1  
(1) (iv) 50.73(a)(2)(ii) 50.73(a) (2)(viii)(B) below and in Tex1, NRG Form 366A) 20.405(a)(1  
)(v) 50.73(a) (2) (iii) 50.73(a)(2)(x)
)(v) 50.73(a) (2) (iii) 50.73(a)(2)(x)

Revision as of 15:32, 25 April 2019

LER 94-001-00:on 940105,discovered More than One Inoperable Apri Per Bank.Caused by Design Error.Position Indicators Calibrated & TS 3.0.3 exited.W/940203 Ltr
ML18100A877
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/03/1994
From: PASTVA M J, VONDRA C A
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-001, LER-94-1, NUDOCS 9402180173
Download: ML18100A877 (5)


Text

.l

  • Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Salem Generating Station U. s. Nuclear Regulatory Commission Document Control Desk Washington-, DC 20555

Dear Sir:

SALEM GENERATING STATION LICENSE NO. DPR.,..70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 94-001-00 February 3, 1994 This Licensee Event Report is being submitted pursuant to the requirements of Code of Federal Regulation lOCFR50.73(a)

(2) (i) (B). Issuance of this report is required within thirty (30) days of event discovery.

MJPJ:pc Distribution 940203 S ADOCK 05000272 PDR Sincerely yours, //;* £//

c. A. Vondra General Manager -' Salem Operations rc"LL I I I 95-2189 REV 7-92

NRC FOJ3M 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 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 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. FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3) Salem Generating Station -Unit 1 05000 272 1 OF04 TITLE (4) TS 3.0.3 Entries; More Than One Inoperable ARPI Per Bank. EVENT DATE (5) LER NUMBER (6 REPORT NUMBER (7l OTHER FACILITIES INVOLVED (8) SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR NUMBER MONTH DAY YEAR 05000 311 NUMBER Salem Unit 2 FACILITY NAME DOCKET NUMBER 01 05 94 94 --001 --00 02 94 05000 03 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more (11 l MODE (9) 2 20.402(b) 20,405(c)

50. 73(a)(2)(iv) 73.71(b) POWEI=l 20.405(a)(1

)(i) 50.36(c) (1) 50. 73(a)(2)(v) 73.71 (c) LEVEL (10) 000 20.405(a)

(1) (ii) 50.36(c) (2) 50.73(a)(2)(vii)

OTHER .

20.405(a)

(1) (iii) x 50.73(a)(2)(i)

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 Tex1, NRG Form 366A) 20.405(a)(1

)(v) 50.73(a) (2) (iii) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER 12\ NAME TELEPHONE NUMBER (Include Area Code) M. J. Pastva, Jr. -LER Coordinator (609) 339-5165 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORTl13l CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR YES SUBMISSION (If yes, complete EXPECTED SUBMISSION DATE) NO DATE (15) x ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16) -Intentional Technical Specification (TS) 3.0.3 entries were made: for Unit 2 on 1/5/94, from 1637 to 1642 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.24781e-4 months <br />, and on 1/16/94, fr_om 0037 to 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, and for Unit 1 on 1/24/94, from 2215 to 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br />. This was done to permit calibrating the respective Analog Rod Position Indicator (ARP!) control Board dual indicator modules for Unit 2 control rods 2B4 and 1D2 and for Unit 1 control rods 2Al and 2B2. Calibrating the indicators required removing the dual indicator modules, which rendered ARP! for subject rods and for the rods sharing the same module inoperable:

2B3 and lDl (Unit 2)* and 2A2 and 2Bl (Unit 1). In each case, actual rod positions (per group demand) were correct. The root cause of these events is design of ARP! position.indicators requiring entering TS 3.0.3 whenever ARP! calibrations are performed.

The subject position indicators were calibrated and TS 3.0.3 was exited. A Night Order Book (NOB) entry was made, on 1/27/94, to provide guidance/restrictions for ARP! Dixon indicator calibrations and TS 3.0.3 entries. An Information Directive will be issued to formalize the 1/27/94 NOB entry. NRG FORM 366 (5-92)

-* LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating station Unit 1 DOCKET NUMBER 5000272 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse

  • -Pressurized Water Reactor LER NUMBER 94-001-00 PAGE. 2 of 4 Energy Industry Identification System (EIIS) codes are identified in the text as {xx} IDENTIFICATION OF OCCURRENCE:

Technical Specification (TS) 3.0.3 Entries On Both Salem Units; More Than One Inoperable Analog Rod Position Indicator (ARPI) Per Bank Event Dates: (Unit 2) 1/5/94 and 1/16/94 (Unit 1) 1/24/94 Report Date: 2/3/94 This report was initiated by Incident Report Nos.94-006, 94-019 and 94-028. CONDITIONS PRIOR TO OCCURRENCE: (Unit 2) 1/5/94: Mode 1 Reactor Power 34% Unit Load -300 MWe 1/16/94: Mode 1 Reactor Power 100% Unit Load -1180 MWe (Unit 1) Mode 2 Reactor Power lOE-8 Amps Unit Load -o-DESCRIPTION OF OCCURRENCES:

Intentional TS 3.0.3 entries were made: for Unit 2 on January 5, 1994, from.1637 to 1642 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.24781e-4 months <br />, and on January 16, 1994, from 0037 to 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br />, and for Unit 1 on January 24, 1994, from 2215 to 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br />. This was done to permit calibrating the respective ARPI {AA} Control Board dual indicator modules for Unit 2 control rods 2B4 and 1D2 and Unit 1 control rods 2Al and 2B2. The calibration process rendered ARPI inoperable for the subject rods and for the rods sharing the same dual indicator module: Unit 2 rods 2B3 and lDl and Unit 1 rods 2A2 and

  • 2Bl. In *each case, actual rod positions (per group demand) were correct. ANALYSIS OF OCCURRENCES:

ARPI operability is required to determine individual control* rod position and ensure compiiance with control rod alignment and insertion limits assumed in the accident analyses.

ARPI provides actual rod position to the following locations:

the Control Board dual channel position indicator modules (supplied by Dixon), the Safety Parameter Display System (SPDS), the main process P250 computer,.and iocally via the digital multimeter (DMM) ._

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 --DOCKET NUMBER 5000272 ANALYSIS OF OCCURRENCES: (cont'd) LER NUMBER 94-001-00 PAGE 3 of *4 TS 3.1.3.2.1 addresses the operability requirement of the "Reactivity Control System's" position indicating systems. The indicators are determined operable by verifying that the rod position indication system agrees within twelve (12) steps of the group demand counters.

If more than one ARPI per bank is inoperable, the Limiting Condition For Operation and associated ACTION requirements of TS 3.1.3.2.1 are not met and TS 3. o. 3 therefore applies. -On January 5th, 16th, and 24th, TS 3.0.3 was intentionally entered to allow calibrating the respective ARPI Dixon dual position indicators for control rods 2B4 and 1D2 (Unit 2) and for 2Al anci 2B2 (Unit 1). Calibrating the indicators required removing the dual indicator modules, which rendered the ARP! for subject rods and for the rods sharing the same module inoperable:-

2B3 and lDl (Unit 2) and 2A2 and 2Bl (Unit 1). In each case, actual rod positions (per group demand) were correct. The indicators were then calibrated, ARP! for the affected control rods was restored, and in each case TS 3.0.3 was exited. -APPARENT CAUSE OF .OCCURRENCES:

The root cause of these events is "Design, Manufacturing, Construction/Installation", per NUREG-1022.

Design of ARPI position indication is such that two rods share each Dixon indicator module. Consequently, TS 3.0.3 is entered whenever the ARP! position indicator

-modules are removed from service for calibration.

PRIOR SIMILAR OCCURRENCES:

Prior events requiring TS 3.0.3 entry, due to ARP! control rod design concerns, have occurred on both Salem Units, as reported in LERs

  • 272/93-007-00, 311/92-016-00, and 311/93-010-00.

As a result of these events, System Engineering has developed an ARP! trending data base to identify problem-electronic modules. In addition, the industry Rod Control User's Group has recognized an industry-wide problem with ARP! System drift. Recommendations from this group and the vendors will be used to develop appropriate action. -SAFETY SIGNIFICANCE:

These events did not affect the health and safety of the public. With entry into TS 3.0.3, these events are reportable to the NRC pursuant to Code of Federal Regulations lOCFR 50.73(a) (2) (i) (B). TS required actions were met for these events. In each case, actual rod positions (per group demand) were correct, with only the Control Board indication wrong. Verification of position was available via the SPDS, the P250 computer, and local DMM.

. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 CORRECTIVE ACTION: DOCKET NUMBER 5000272 LER NUMBER 94-001-00 PAGE 4 of 4 The position indicators of the affected rods were calibrated and TS 3.0.3 was exited. A Night Order Book (NOB) entry was made, on January 27, 1994, to provide guidance/restrictions for ARPI Dixon indicator calibrations and TS 3.0.3 entries. An Information Directive will be issued to formalize the above-referenced NOB entry. PSE&G will continue to participate in the industry Rod Control User's Group efforts to resolve the industry-wide problem with ARPI System drift. ,/} / MJPJ:pc SORC Mtg.94-011 I ,i_ General Manager -Salem Operations