ML18022A513

LER 87-022-00:on 870402,Tech Spec 3.3.3.10 Discovered Violated Due to Flow Estimates Taken at Beginning & End of Radioactive Releases on 870327,28 & 0401 Instead of Every 4 H.Caused by Inoperable Flow Rate instrument.W/870430 Ltr

ML18022A513
Person / Time
Site:	Harris
Issue date:	04/30/1987
From:	Hudson O, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-870416-(O), LER-87-022, LER-87-22, RO-870416-(O), NUDOCS 8705180245
Download: ML18022A513 (5)

Text

REQUL RY INFORNATION DISTR IBUTI SYSTE (R IDS) ~r ACCESSION NBR: 8705180245 DOC. DATE: 87/04/30 NOTARIZED: NO DOCKET FACIL: 50-400 Shearon Harris Nuclear Pouer Planti Unit 1~ Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION HUDSON> O. N. Caro l ina Power Zc Lig h t,Co. WATSON> R. A. Carolina Power 5 Light Co. RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-022-00: on 870327-28 5 0401-02>flow estimates made at Zc end of releases> in violation of Tech Specs 3. 3. 3. 10. 'tart Caused bg personnel error. Night order (written stressing importance of procedure 8c Tech Spec compliance. 8/870430 tr. DISTRIBUTION CODE: IE22D COPIES RFCEIVED: LTR ENCL SIZE: TITLE: 50. 73 Licensee Event Report (LEH)i Incident Rpti etc. NOTES: Application for permit rene@.al filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/MANE LTTR ENCL ID CODE/MANE LTTR ENCL PD2-1 LA 1 ,PD2-1 PD 1 1 BUCKLEY B 1 1 INTERNAL: ACRS NICHELSON 1 1 *CRS MOELLER 2 2 AEOD/DOA 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 DEDRO 1 1 NRR/DEST/ADE 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 NRR/DEST/ELB 1 1 NRR/DEST/ ICSB 1 N'RR/DEST/MEB 1 NRR/DEST/}'}TB 1 1 NRR/DEST/PSB 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 NRR/DREP/EPB 1 1 NRR/DREP/RAB 1 1 ViRR/DREP/RPB 2 2

                      }A ILRB           1      1       NRR/PNAS/PTSB            1      1 REG    FIL         02             1       RES SPEIS> T             1 R    ~     FILE    01             1 EXTERNAL: EQSQ      GROH> N            5      5       H   ST LOBBY WARD        1      1 LPDR                              1       }'HRC  PDR               1 NSIC HARRIS. J             1      1       }'~SIC NAYS> 9           1 TOTAL NUNBER OF COPIES REQUIRED:           LT1R      43    ENCL   41

NRC Form 380, U.S. NUCLEAR REOULATORY COMMISSION (043) APPROVED OMB NO. 3150010e LICENSEE EVENT REPORT (LER) EXPIRES: 8/31/88 FACILI'TY NAME (I) DOCKET NUMBER (2) PA E 3 Shearon Harris Nuclear Power lant o. 1 0 5 0 0 0 1 OF TITLE Ie) Technical S ecification Violation Missed Flow Rate Estimate EVENT DATE (5) LER NUMBER (8) REPORT DATE (7) OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YEAR + SEOUENTrAL:>g NUMBER M REVc)ION NUMBER MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(S) 0 5 0 0 0 0 402 8 7 8 7 022 0 0 0 4 3 0 8 7 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REOUIREMENTS OF 10 CFR (): (Check onr or more of thr folloqlnpi (11 POWER

            '0A02(b)

OPERATINO MODE (0)

                            ]

20AOS( ~ l(1)(il 20AOS(e) SOW(c)(1) (i(i) 50.73(el(2) (iv) 50.73(e) (2)(v) 73.71(b) 73.71(c) LEVEL (10) 5 0 20AOS(e l(1) liil 50.38 (cl (2) 50.73(el(2) (vill OTHER ISprcify in Abttrrct

        "                              20AOS(e) l1) (iiil brlovv end In yrxt, HRC Form g(%$                                                                               50.7 3(e) (2) (I)                  50.73(el(2) (viii)(A)                      366AI 20AOS(e l(1) (Iv)                           50.73(e) (2) (8 I                  50.73(el(2) (v(4)(B) 20AOS(e) (I ) (v)                           50.73(e ) (2)                      50.73(e) (2)(x)

L,ICENSEE CONTACT FOR THIS LER (12) NAME TELFPHONE NUMBER AREA CODE

0. N. Hudson, Senior Engineer Regulatory Compliance COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC. TVRER EPORTABLE TO NPRDS g'AUSE g SYSTEM COMPONENT MANUFAC. TURER EPORTABI.E TO NPRDS FZa8748 SUPPLEMENTAL REPORT EXPECTED (Ie) MONTH DAY YEAR EXPECTED SUBMISSION YES (if yrr, completr EXPECTED SIIBktISSIDH DATE) DATE (15) NO ABSTRACT ILlmlt to Ir00 s>>crt, I e., epproxlmetrly flftern tlnplr.corer typewritten lined (18) The Shearon Harris Nuclear Power Plant was operating in Mode 1 at approximately 50K power. Radioactive releases from the Floor Drain Waste Monitor Tank l&2A were made on March 28, 1987 and on April 1, 1987. The Cooling Tower Blowdown flow rate instrument was inoperable during these releases. Technical Specification 3.3.3.10 allows releases to continue with this instrument inoperable provided flow rates are estimated every four hours during the release. For both of these releases, flow estimates were actually made at the beginning of the releases and 7~< to 8 hours into the releases in violation of the Technical Specification requirement. These errors were discovered on April 2, 1987 during routine log review. 8705180245 870430 PDR ADOCK 05000400 8 PDR

                                                                                                             ~~Qg g I) r NRC Form 388 (Be)3)

U.S, NUCLEAR REGULATORY COMMISSION NRC Form 366A (94)3) LICENS EVENT REPORT (LER) TEXT CONTI ATION APPROVEO OMB NO. 3150M)04 EXPIRES: 8/31/88 FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6I PAGE (3) YEAR SEQVENTIAL REVISION NUMBER NUMBER Shearon Harris Unit 1 OF 0 5 0 0 0 TEXT /1mor>> <<>>c>> lr 1>>Soil/, IIF>> //R/Oo>>/HRC %%drrrr 35843/ (IT) Descri tion of the Event On March 27, 1987, the Shearon Harris Nuclear Power Plant was operating in Mode 1 at approximately 50X power. A radioactive release was to be made from the Floor Drain Waste Monitor Tank 1&2A. The discharge permit (87-0544) indicated that the Cooling Tower Blowdown flow instrument was inoperable. The flow instrument was inoperable due to a modification being installed on the Cooling Tower"Blowdown System. Technical Specification 3.3.3.10 allows effluent releases to continue with this instrument inoperable provided the flow rate is estimated at least once per four hours during actual releases. The corresponding release procedure (OP-120.09.02) also requires flow rate estimates every four hours under these conditions. Flow estimates were actually made at the start of the release at 2250 on March 27, at 0610 on March 28, and near the end of the release at 0950 on March 28. A period of 7 hours and 20 minutes elapsed between the first flow estimate and the second. On April 1, 1987, another release was planned from the Floor Drain Waste Monitor Tank 1&2A. The plant was still operating in Mode 1 at approximately 50X power. Again, the discharge permit (87-0574) indicated that the Cooling Tower Blowdown flow instrument was inoperable. A flow estimate was made at the start of the release at 1205 on April 1 and near the end of the release at 2000 on April 1. A period of 7 hours and 55 minutes elapsed between the first and second flow estimates. Both of these errors were discovered during a routine log review on April 2, 1987. Cause The cause of the event in both cases was personnel error', the Radwaste Control Operators did not follow approved written procedures which require flow estimates every four hours. The Radwaste Control Operator in each case made a flow estimate at the start of the release, but did not do the flow estimate four hours after the start of the release as required by Technical Specifications and the Operating Procedure. Flow estimates vere made by the next shift 7< to 8 hours into the releases. It should be noted that the Floor Drain Waste Monitor Tanks are the only tanks which require greater than four hours to release. NRC FORM SEEA *U.S.GPO:1986 0-624 538/455 (963)

NBC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (94)3) LICEN EVENT REPORT (LER) TEXT CONTI ATION APPROVED OMB NO. 3150-0104 EXPIRES: 6/31/BB FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) YEAR SEOUENTIAL REVISION NUMSER NUMSER Shearon Harris Unit 1 OF 0 5 0 0 0 TE)O'//'rr>>rs <<>>I>> /4/sl/rsr/ Iroa //I/Or>>/ HRC Forrri 3664 3/ (IT)

             ~Anal     sis This event is being reported in accordance with 10CFR50.73(a)(2)(i)(B) since the Technical Specification requirement to estimate flow rate every four hours was not followed.

There were no effects on the health and safety of the general public since the Cooling Tower dilution flow was maintained during the entire period of the releases. No.safety systems were affected by this event. There have been no previous similar events. Corrective Actions

1. Upon discovery of the error, a night order was written on April 2, 1987 to stress the importance of procedure and Technical Specification compliance.

2. The Radwaste Shift Foreman will discuss this event with the Radwaste Control Operators on their first shift following discovery of the event.

3. A copy of this LER will be routed to all Radwaste Operators and Foremen for review by each shift.

NRC FORM SSSA *U.S.GPO:(966.0.624 536/455 (94)3)

CPKL Carolina Power & Lighl Company HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 April 30, 1987 File Number. SHF/10-13510C Letter Number'HO-870416 (0) U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 87-022-00 Gentlemen'. In accordance with Title 10 to the Code of Federal Regulations, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportabIe occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983. Very truly yours, R. A. Watson Vice President Harris Nuclear Project RAW'skm Enclosure cc: Dr.'. Nelson Grace (NRC RII) Mr. B. Buckley (NRR) Mr. G. Maxwell (NRC SHNPP) MEM/HO-8704160/PAGE 1/Osl}}