ML18096B187

LER 92-025-00:on 921206,identified That Analog Rod Position Indications for CR in Violation of TS 3.0.3.Caused by Equipment Failure.Work Order Has Been Initiated to Replace 2DI & 1D4 Signal Conditioning modules.W/930105 Ltr

ML18096B187
Person / Time
Site:	Salem
Issue date:	01/05/1993
From:	Pollack M, Vondra C Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-92-025, LER-92-25, NUDOCS 9301070182
Download: ML18096B187 (5)

Text

.

PS~G Pui'..1ic Service Electric *and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station January 5, 1993

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 92-025-00 Thi~ Licensee Event Report is being submitted pursuant* to the requirements of th~ Code of Federal Regulations 10CFR 50.73(a) (2).(i) (B). This report is required to be issued within thirty ( 3 O) days of event discovery. -

Sincerely yours,

.. ;/ ~-If i //) /

• 1/Ju~lf{Mr c .. A Vondra -

General.Manager -

Salem Operations MJP:pc Distribution

/ If I 1-fe!"

- .(i 9.301070182 930105 .

PDR ADOCK 05000272 s PDR

l\lRC FOR!l;! 366 .U.S. NUCLEAR REGULATORY COMMISSION

, (6-891 APPROVEO OMB NO. 3150-0104 EXPIRES: 4/30/92 ESTIMATED BURDEN PER RESPONSE .TO COMPLY WTH THIS INFORMATION COlLECTION REQUEST: 50.0 HRS; FORWARD LICENSEE EVENT- REPORT (LER)

. COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO

• • .I THE PAPERWORK R'EDUCTION PROJECT (3150-0104), OFFICE I

OF MANAGEMENT AND BUDG.ET, WASHINGTON, DC 20503.

FACILITY NAME (1)

Salem Generating Sta ti op

- Unit 1 DOCK.ET NUMBER (2) 01s1010101 21 712 I

, PAGE 131 OF 0 I 4 TITLE (4)

Tee:h Snee 3.0.3 entry; more than one analog rod position indicator per bank .. tl.npperable.

EVENT DATE 15.l* LER NUMBER (6) REPORT DATE (71 OTHER FACILITIES INVOLVED (81 MONTH DAY YEAR YEAR *:*:*:*:*:* SEQUENTIAL :::::::::: REVISION DAY YEAR FACILITY NAMES DOCKET NUMBERISI

• .*.*.*.*.* NUMBER :::::;:::: NUMBER MONTH i> 1s Io Io* I o I I I

-11 2 ol6 9 *2 91 2

- ol 2 Is - o lo 0!1 ol s 91 2 0 I5 I0 I0 I 0 I I I OPERATING THIS REPORT IS SUBMITTED*PURSUANT TO THE R~QUIREMENTS OF 10 CFR §: (Chock one or more of the following) (111 MODE (9) 1 20.402(b)

,....__ 20.405(cl ,_ 50.73(1)(2)(iv)

,....__ -73.71(b)

POWER

• LEVEL (10) l 1; 010 - 20.406(11(1 llil 20.406(1)(1 l(ii) ---- 60.38(c)(1) 50.38(c)(2) 50.73(1)(2)(v) 50.73(1)(2)(vii)

,....__ 73.71 (cl OTHER (Spacify in Abstract

'

: : ':~*: : *: : : : :*: .:-.:=: : : : : :*: ': : : : : : : : : -

~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:~:i:~:~:~:~:~:~:~:~:

20.406(1)(1 l(iii) 20.405(1)(1 l(lv) 20.405(1)(1 )(y)

-- x 50.73(1112Hil 60.73(1)(2l(ii) 50.73(1)(2)(iii) 60.73111(2)(viii)(AI 50.73(11(2)(viii)(BI 50.73(1)(211*1 .

below tJnd in Toxr, NRC Form 366A)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE M.J. Pollack - LER Coordinator - 610 19 313191-12 IO 12 12 COMPLETE ONE LINE FOR EACH COMPONENT .FAILURE OESCRIBED IN THIS REPORT (13)

REPORTABLE 1:-:*:-:-.** ...,,... .....,. .......

CAUSE SYSTEM COMPONENT MANUFAC*

TUR ER TO NPRDS "'""* .,.,,...... ,.,........,,.......

, CAUSE SYSTEM COMPONENT MANUFAC*

TUR ER REPORTABLE TO .NPRDS .......... . ,..... .....,.

- [::::::: *.*. ...........

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B AIA I IM 10 ID H I Oi 115 *.-.*:*. ..., ..., I I I I I I I ..... *:-: :-::*:

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I I I I I i I  !::::::::::::: ....... ,...........

........ I I I I I .I I  !:. :,:: ::::::::...........

' MONTH DAY YEAR SUPPLEMENTAL REPORT EXPECTED 1141

'EXPECTED rxi SUBMISSION "J YES (If V"'* complete EXPECTED SUBMISSION DATE) NO DATE 1151 I I I

. ABSTRACT (Limir to 1400 spsces. i.e .. approximately fiftef!n single.space typewritten /in.es} (161 On 12/6/92, at 1743 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.632115e-4 months <br />, during full power operation, the Control Room Operator identified that Analog Rod Position Indications (ARPis) for Control Rods 104 and 2Dl. were indicating greater than a+/- 12 step deviation from their group demand counter. Technical Specification 3.1.3.2.1 addresses.the operability requirement of *the "Reactivity Control System's" position indicating systems. Actions required when more than one ARP! per bank is inoperable exceed the Tech. Spec.

3.1~3.2.l Limiting Condition For Operation; therefore,. actions associated*

with Tech. Spec. 3.0.3 apply (and was entered *on 12 / 6 / 9 2 ) . On 12/6/92, at 1816 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.90988e-4 months <br />, the *2n1 control rod position indication was corrected by adjustment of the signal conditioning module. Tech. Spec .. 3.0.3 was.

subsequently exited. Technical Specification Action 3.1.3.2.la.a

• remained in affect until the 1D4 control rod position indication was.

corrected, at 1827 hours0.0211 days <br />0.508 hours <br />0.00302 weeks <br />6.951735e-4 months <br />. The cause of the ARPis having greater than.+/-

12 step deviation from their group demand counter, for the two (2) control rods, is equipment failure. Signal conditioning modul*e drift was responsible for the two (2) control rods to be indicating greater than +/-

,12 steps from their group demand counter. The ARP! system electronics s~ttings, associated with the Westinghouse Signal Condition Module, will ha.ve some drift. aowever, it*is expected that this drift will not exceed the acceptable limit of + 12 steps from group demand within the 18 month calibration period. The signal conditioning module for the 2Dl and 1D4 control rod indicators are being rTplaced.

NRC .Form.366 16-891

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION

• ~~~7~~~~~~~~~~~~~~~~~~~~~~--"'-~~...,,.;...._,..~~~~~~~~-

S al em Generating Station DOCKET NUMBER LER NUMBER PAGE Unit 1 5000272 92-025-00 2 of 4 PLANT AND SYSTEM IDENTIFICATION:

Westinghouse -.Pressurized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}

IDENTIFICATION OF OCCURRENCE:

• Technical Specification 3.0'.3 entry; more than one analog rod position indicator per bank inoperable Event Dates:* 12/06/92 Report Date:

• 1/05/93 This report was initiated by Incident Report No.92-803.

CONDITIONS PRIOR TO OCCURRENCE:

Mode 1 Reactor Power 100%-- Unit Load 1150 MWe On,12/6/92 at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, a power increase from 81% to 100% was initiated. As of 0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />, reactor power was ioo% with the control rods in manual.

DESCRIPTION OF OCCURRENCE:

On December 6, 1992, at 1743 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.632115e-4 months <br />, during full-power operation, the Control Room Operator identified that Analog Rod Position Indications (ARPis) for Control Rods 1D4 and 2Dl were indicating greater than a +/-

12 step deviation from their group demand counter.

Technical Specification -3.1.3.2.1 addresses the operability requirement of the "Reactivity Control System's" {AA} 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. Actions required when more than one ARPI per b~nk is inoperable exceed the Technical Specification 3.L3.2.l Limiting Condition .For Operation; therefore, actions associated with Technical Specification 3.0.3 apply (and was entered on December 6, 1992).

Technical S~ecification 3.0.3 states:

"When a Limiting Condition for Operation is not met except as-provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in a MODE in which th~ s~ecification does n9t apply by placing it, as applicable,

.in:

. 1. At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

' ~

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION

---

~~'-----------------_;:_--------------------------------------..-------------~

Salem Generating Station DOCKET.NUMBER LER NUMBER PAGE unit 1 5000212 92-025-00 3 of 4 DESCRIPTION OF OCCURRENCE: - (cont'd)

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the ACTION-requirements, the ACTION may be taken in -

accordance with the specified time limits as measured from the

-time of failure to meet the Limiting Condition of Operation.

Exceptions to these requirements are stated -in the individual specifications~" *

• On December 6, 1992., at 1816 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.90988e-4 months <br />, the 2Dl control rod position indication was corrected by adjustment of the signal -conditioning

_module. Technical Specification 3. o. 3 was subsequently exited.

Technical Specification Action 3.1.3.2.la.a remained in affect until the lD~ control rod position indication was corrected, at 1827 hours0.0211 days <br />0.508 hours <br />0.00302 weeks <br />6.951735e-4 months <br />.

APPARENT CAUSE OF OCCURRENCE:

The cause of the ARPis having greater than +/- 12 step deviation from their group demand counter, for the two '(2) control -rods, is equipment failure. Maintenance-I&C investigation identified that signal conditioning module drift was responsible for the two (2) control rods to be indicating greater than+/- 12*st~ps from their group demand counter.

The ARPI system electronics settings, associated with the Westinghouse Signal Condition Module, will have some drift . . However, it is expected that this drift wiil not exceed the acceptable limit of +/- 12 steps from group demand within the 18 month calibration period ..

ANALYSIS-OF OCCURRENCE:

Operability of the ARPis is required to determine control rod position. This ensures co~pliance with control rod alignment and insertion limits assumed in the accident analyses. Investigation of this event showed that actual rod positions (per group demand) were correct, with ortiy.the indication being wrong. However, -had a control rod actually been misaligned, the appropriate Technical Specification Action Statement requirements would have been met.

The false rod positioning indication did not affect the health or safety of the public; however, since Technical Specification 3.0.3 was entered, this-event is-reportable to the Nuclear Regulatory Commission in accordance with Code of Federal Regulations 10CFR

50. 73 (a) (2) (i) (B). -

CORRECTIVE ACTION:

As stated in the* Description of Occurrence section, the 2Dl and 1D4 control rod position indications were corrected by adjustment of their sign~l conditioning modules.

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION

~~~0;...._~~~~~~~~---'-~~~~~~~~~~~~~~~~~~~~~~~~~~

Salem Generating station DOCKET *NUMBER LER NUMBER PAGE Unit 1 5000272 92-025.;..00 4 of. *4 CORRECTIVE ACTION: (cont'd)

A work order has be.en initiated to :r*eplace the. 201 and 104 signal conditioning modules.

system ~ngineering is continuing its review of this event and similar prior events. Additional corrective action will be implemented based

~pon this review~

fld~

enera1* anager -

, Salem Operations MJP:pc SORC Mtg.93-001