ML18040A912

LER 88-018-00:on 880824,discovered That RWCU Pump Room Ambient Temp Sensor Not Installed Per Design.Caused by Lack of Installation Detail on Design Documents for Steam Leak Detection Sys.Tech Spec Change submitted.W/880923 Ltr

ML18040A912
Person / Time
Site:	Susquehanna
Issue date:	09/23/1988
From:	Byram R, Ryder T PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-018-05, LER-88-18-5, PLAS-338, NUDOCS 8809290378
Download: ML18040A912 (5)

Text

AC~~ELZRATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8809290378 DOC.DATE: 88/09/23 NOTARIZED- NO DOCKET FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 05000387 "

AUTH. NAME AUTHOR AFFILIATION RYDER,T.S. Pennsylvania Power S Light Co.

BYRAM,R.G. Pennsylvania Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-018-00:on 880824,one channel of RWCU sys area high temp isolation instrument found inoperable.

W/8 ltr. iI DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR g ENCL (

TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

SIZE:

D NOTES:LPDR 2 cys Transcripts. 05000387IB RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL A PD1-2 LA 1 1 PD1-2 PD 1 1 THADANI,M 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DS P/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB SD 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB SD 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR/DRIS/SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 REG FILE 02 1 1 RES TELFORD,J 1 1 1 1

'RES/DSIR/EIB 1 1 GNl FILE 01 1 1 EXTERNAL EG&G WILLIAMSE S 4 .4 FORD BLDG HOY I A 1 1 R

H ST LOBBY WARD 1 1 LPDR 2 2 NRC PDR 1 1 NSIC HARRIS,J 1 1 I NSIC MAYS,G 1 1 D

NOTES: 2 2 8

A TOTAL NUMBER OF COPIES REQUIRED: LTTR 49 ENCL 48

NRC Form 388 US. NUCLEAR REGULATORY COMMISSION (9-83)

APPROVED OMB NO. 31604104 EXPIRES: 8/31/SS LICENSEE EVENT REPORT (LER)

FACILITYNAME (II DOCKET NUMBER (2I PACE 3 Susquehanna Steam Electric Station Unit 1 0 5 0 0 0 8 7 1 OF0 TITLE (4)

I One Channel of RWCU System Area High Temperature Isolation Instnmant Found Inoperable EVENT DATE (5) LER NUMBER (SI REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR @ StOVENTIAL

'UMBER I 8ES RE~

NUMBER MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S) 0 5 0 0 0 0 8 2 4 8 888 0 1 8 00 092 3 88 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT TO THE REOUIREMENTS OF 10 CFA ('I t (Check onr ot mote ol tbr folios(for) (11)

OPERATINO MODE (9) 20A02(b) 20AOS(c) 60.73(sl(2)(lv) 73.71(b)

POWER 20.405(e) (1) (II 5028(c) (1) ~

60.73(e) (2l(v) 73.71(c)

(2)(rill LEVEL 1 p p 20.405(e)(1)(N) 50.38(c) (2) 60.73(e)(2)(ril) OTHER (Specify In Abttrrct below end In Test, HI(C Form P'gA" 20.405(e) 0)(ill) X 60.73(s)(21(II 50.73(e) (2)(vill)(A) 3EBAJ 20AOS(s)(t)(lvl 50.73(e)(2)(ll) 50.73 (sl (8) 20.405(s)(t I(v) 50.73(s) (2) (IB) 60.73(e) (2)(s)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE T.S. der Pn)er Production En ineer 71 754 2 2 3 5 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC. AEPORTABLE MANUFAC EPORTABLE CAUSE SYSTEM COMPONENT TO NPADS CAUSE SYSTEM COMPONENT TURER 'URER TO NPRDS o

'w

.w aa v'.t, ..,,....

I<<RM SUPPLEMENTAL REPOAT EXPECTED (14) MONTH DAY YEAR EXPECTED SU 8 M I SS ION DATE (16)

YES (II yrs, complrtr EXPECTED SIIB4(ISSIOH OATEI X NO ABsTRAcT (Limit to lr00 tpecrt, I.e., epptoslmetrly fi(tern tlnrfreprce typewritten llnNI (18)

On August 24, 1988, it was discovered that the HWCU Pump Room ambient temperature sensor, TE-G33-1N016A, was not installed per design. TE-G33-1N016A was discovered to have been installed in a location in which detected a HWCU steam leak in the HNCU Pump Room area. The installation error it would not have was discovered during a walkdown of the steam leak detection system. The walkdawn had been initiated in response to recent problems identified on the MSL DT trip logic. Root cause of this event was attributed to a lack of installation detail on the design documents for the steam leak detection system. The ventilation drawing used for identification of instrument location for TE-G33-1N016A was vague and did not clearly shaw the mounting location.

This resulted in the temperature sensor being installed inside 'the main steam tunnel exhaust duct instead of being installed on the wall of the HWCU pump rocm. The event has been determined to be reportable per 10CFR50.73(a)(2)(i)(B), in that one trip logic channel for the HNCU Pump Room HWCU leak detection ambient temperature trip logic has been inoperable prior to August 24, 1988 and would not have been able to perform its design function. A new temperature instrument was installed in the proper location within the HWCU Pump Room and the original temperature instrument was left as a spare device in the MSL exhaust duct. A task force is in the process of reviewing the entire steam leak detection system for adegcacy and will be providing recammndations for permanent corrective action. The findings of this task team will be reported in a follawup to LER 88-017-00 (Docket 50-387) and this LER will not be updated.

SSO 3 ('S0929037S PDR ADOCK 050 03S7 I PDC NRC Form 3SS (983)

NRC Form 366A U.S. NUCLEAR REOULATORY COMMISSION (943) r LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3150M(04 EXPIRES: 8/31/68 FACILI'TY NAME (1) OOCKET NUMBER (2) LER NUMBER (6) PACE (3)

%ca EEQUENTIAL iPSI REvlsloN YEAR CON NVMSCR (~" NVMCER Unit 1 Sus ehanna Steam Electric Station 05000387 8 8 018 0 0 0 30F 0 3 TEXT ///more space /s a/O/rarL usa ///Oora/HRC Form365rE's/03)

CORRECZIVE ACZIONS A request for enforcement discretion was subnitted to the NHC for relief fran Technical Specification 3.3.2. The provisions of this technical specification require placing the trip system in the tripped condition or closing the affected system isolation valves either of which would have caused isolation of HhUJ fran the reactor vessel until the inoperable channel of HNCU temperature isolation instrumentation could be restored to operable status. Having HNCU isolated fran the reactor vessel for the extended period of time anticipated to return the inoperable channel to operable status would result in significant degradation of reactor coolant chemistry and could eventually require shutting the unit. dawn. The request was granted for the period of time ending at, 11:00 a.m. on August 29, 1988. On August 26f 1988 a new temperature instr(ment was installed in the proper location within the HNCU Pump Roan and the original temperature instrument was left as a spare device at its location in the main steam tunnel exhaust duct. Appropriate drawings were revised to reflect the new plant configuration for these devices. A task team had been previously formulated to review the subject of steam leak detection. An in-depth review

, will be performed for all leak detection systems including the HNCU, Residual Heat Removal (RHR, EIIS Code: BO), Reactor Core Isolation Cooling (RCIC, EIIS Code: BN), High Pressure Coolant Injection (HPCI, EIIS Code: BJ), and MSL Leak Detection Systems. Calculations and design bases will be reviewed for adequacy and determination of the root cause and appropriate long-term corrective actions will be performed. The findings of this task team will be reported in a followup to LER 88-017-00 (Docket 50-387) and this LER will not be updated.

ADDITIONAL INFORMATION Failed Caagmnent Identification: Not applicable.

Previous Similar Events: Not Applicable NRC fORM 366A *U.S.GPO:(985&524 538/455 (983)

NRC Form'3SBA U.S, NUCLEAR REGULATORY COMMISSION (543)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3)50-GIGA EXPIRES: 5/3)/SS FACILITYNAME l)l DOCKET NUMBER (2) LER NUMBER (5) PAGE (3)

"EAR ')k SEOVENTIAL NUMBER REVISION NUMBER Unit 1 Susquehanna Steam Electric Station o 5 o o o 3 8 7 8 8 0 0 2 OF 0 3 TEXT //fmoro F/>>co /F /Fr/ro ~ / Iroo ////Or>>/ HRC Forrrr 35EA'F/ 07)

DESCRIPTION OF EVEÃZ On August 24, 1988, EIIS Code: CE) Pump Roam it was ambient discovered that the Reactor Water Cleanup temperature sensor, TE-G33-1N016A, (HWCU, was not installed per design. TE-G33-1N016A had been installed in a location in which it would not have detected a steam leak in the HWCU Pump Roam area. The installation error was discovered during a walkdown of the steam leak detection system. The walkdown had been initiated in response to recent problems identified on the Main Steam Line (MSL, EIIS Code: SB) differential temperature trip logic which were reported in LER 88-016-00 (Docket 50-387) .

CAUSE OF EVENT Root cause of this event was attributed to a lack of installation detail on the design documents for the steam leak detection system. The ventilation drawing (V-28-5) used for identification of instrument location for TE-G33-1N016A was vague and did not clearly show the mounting location. This resulted in the te(T)perature sensor being installed inside the main steam tunnel exhaust duct instead of being installed on the wall of the RÃCU pump roan.

REPORTABILITY/ANALYSIS The event had been deteznuned to be reportable per 10CFR50.73(a) (2) (i) (B), in that one trip logic channel for the HNCU Pump Room HNCU leak detection ambient te(nperature trip logic has been inoperable prior to August 24, 1988 and would not have been able to perform its design function. Section 7.3.1a.2.4.1.9, 6

.10 of the FSAR provide discussion on the various methods of leak detection available to detect a steam leak associated with the HWCU system. "Diversity of trip initiation signals for RWCU system line break is provided by high differential flow, high flow, ambient and differential temperature, and Reactor Vessel low, low water level, Level 2. An increase in differential flow, space taT)perature, differential temperature, or low Reactor Vessel water level will initiate HWCU isolation." With exception of this channel and the penetration room DT detection, inoperable prior to August 5, 1988 as reported in LER 88-017-00 (Docket 50-'387), the remaining safety systems were in tact to detect a breech in the reactor coolant pressure boundary for the HNCU,system. There was no caT)pranise to the health and safety of the public and no safety consequences occurred.

NRC FORM SBBA o U.S.GPO: I SSS O 52E 535/EES (543)

Pennsylvania Power & Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 21517705151 September 23, l988 U.S. Nuclear Regulatory Carmission Docum nt Control Desk Washington, DC 20555 t[

SUSQUKRNNA STEM EKZCTRIC STATION LICENSEE EVENT REPORT 88-018-00 FILE R41-2 PLAS - 338 Docket No. 50-387 License No. NPF-14 Attached is Licensee Event Report 88-018-00. This event was determined reportable per 10CFR50.73(a) (2) (i) (B) in that one channel of the Reactor Water Cleanup System Area High Temperature isolation instrumentation was- found to be inoperable due to mislocation of a temperature sensor.

R.G.

Superin ent of Plant Susquehanna TSR/mjm cc: Mr. William T. Russell Regional Administrator, Region I U.S. Nuclear Regulatory Ccmtission 475 Allendale Road King of Prussia, PA 19406 Mr. Frank Young Sr. Resident Inspector U.S. Nuclear Regulatory Ccmtission P.O. Box 52 Shickshinny, PA 18655