ML17300B171

LER 87-027-00:on 870728,unit Entered Mode 4 (Hot Shutdown) W/O Meeting Surveillance Requirements for Containment Spray Sys Train B Pump.Caused by Personnel Error.Train a Pump Tests Verified & Procedure revised.W/870105 Ltr

ML17300B171
Person / Time
Site:	Palo Verde
Issue date:	01/05/1988
From:	Haynes J, Malik J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00330-JGH-J, 192-330-JGH-J, LER-87-027, LER-87-27, NUDOCS 8801110406
Download: ML17300B171 (12)

Text

A REGULA INFORM*TION DISTR IBUTI 3YSTEM (RIDS)

ACCESSION NBR: 8801110406 DOC. DATE: 88/01/05 NOTARIZED: NO DOCKET 0 FACIL: STN-5Q-528 Palo Verde Nuclear Station. Unit ii Arizona Publi 05000528 AUTH. NAME AUTHOR AFFILIATION MALIK.J. E. *rizona Nuclear Power ProJect (formerly Arizona Public SeT v HAYNES'. G. Arizona Nuclear Poeer Prospect (formerly Arizona Public Serv REC IP. N*ME RECIPIENT AFFILI*TION

SUBJECT:

LER 87-027-OQ: on 8?0728> unit entered Mode 4 (hot shutdoen) w/o meeting surveillance requirements for containment spray sos Train B pump. Caused bg personnel error. Train A pump tests veri f i ed 5 procedure revised. 4I/870105 ltT .

DISTRIBUTION CODE: lE 2D COPIES RECEIVED: LTR J. ENCL TITLE: 50. 73 Licensee Event Report (LER)i Incident Rpt>

letc.SIZE:

NOTES: Standardized plant, 05000528 RECIPIENT COPIES RECIPIENT CQP IES ID CODE/N*ME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 PD5 PD 1 LICITRAiE 1 DAVIS' 1 1 INTERNAL: ACRS MICHELSQN 1 1 ACRS MOELLER 2 2 AEQD/DQA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEBT/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 NRR/DLPG/GAB 1 ~ NRR/DQEA/EAB 1 1 NRR/DREP/R*B 1 NRR/DREP/RPB 2 2 N N SIB 1 1 NRR/PMAS/ ILRB 1 EQ- FI 02 1 . RES DEPY GI 1 1 RE < ELFORD, J 1 1 RES/DE/EIB 1, 1 RGN5 FILE 01 1 .1 EXTERNAL: EG8cG GROHi M H ST LOBBY NARD.

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~ 4 NAC Form 244 U.S. NUCLEAR REGULATORY COMMISSION (5 53)

APPAOVEO OMS NO. 2)(r04104 LICENSEE EVENT REPORT ILER) EXPIRES: 5/2)IRS SACILI'TY NAME I II DOCKET NVMStA (2l PA Palo Verde Uni t 1 0 5 0 0 0 5 281oF04 TITLE (41 Containment Spray System "B" Train Pump Incorrectly Oeclared Operable EVENT DATK (5I LCA NUMSCR (5) AEPOAT DATE (TI OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YKAA ,yr~r. SRQVRNTrAL NVMRER NUMIIRR MO<<t TH OAY YEAR FACILITYNAMES DOCKET NUMSEA(SI N/A 0 5 0 0 0 0 7 2 887 87 0 2 7 00 01058 8 N/A oi more Of tne fotowinti (I'I 0 5, 0 0 0 OPEAATINO THIS REPORT IS SUSMITTKD PURSUANT' 0 THK AKOUIAKMKNTSOS 10 CSA (It (Crrece one MODE (5) 20.402(RI 20.405(c) 50724) l2) II<<I 72.71(RI Ill(le 20.405(<< I I I I I I) 50.25(c) () ) 50.724)(2) lrI 72.7)(cl

~ OWCA L'EY EL (10) 0 0 0 20.405(e)11) IR) 50.25(<<)(2) 50.72 4) (2) l<<R) OTHER ISpetify In AO<<ttrct oeiow enrf in Tert, fif(C Ferne

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NAME TELEPHONE NUMSKR AREA COOC John E. Malik, (Acting) Compliance Lead 60 23 93 -3 5 27 COMPLETt ONt LINC SOA EACH COMPONENT FAILURE DtSCAIStO IN THIS RCPORT I'l)

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COMPONENT MANUFAC. COMPONENT MANVSAC EPOATAS(.C CAUSE SYSTEM TUAKA TO NPAOS CAUSE SYSTCM TURKR

<<5'O NPADS SUPPLEMENTAL ACPOAT EXPECTED I)el MONTH DAY YEAR EXPECTED SUSMISSION DATE (IS)

YCS Iifyet. <<ompretr EXPECTED SV44<<ISSIO<<i OATKI NO AssTAAOT (Limit to f400 <<petr<<, Ie., rpptorimetety fifteen dnfreopece typrwntten line<<i 115)

At approximately 0947 HST on December 7, 1987, Verde Unit 1 had entered Mode 4 (HOT SHUTDOWN) at approximately 0234 MST on it was discovered that Palo July 28, 1987, without meeting the surveillance requirements for the containment spray system (BE) "BU train pump (P) as specified in Technical Specification (T.S.) 4.6.2.1.b. A test conducted on August 5; 1987, later verified operability of the pump in accordance with T.S. 4.6.2.1.b.

This.e'vent was caused by personnel error as a direct result of an error in an approved procedure. The containment spray pump operability test procedure had been revised on July 8, 1987 to include provisions for pe'rforming Section XI testing of the pump in shutdown cooling mode. The requirements specified in T.S. 4.6.2;l.b require this test to be performed in recirculation mode, however, the revised procedure permitted the test steps necessary to comply with T.S. 4.6.2. l.b to be bypassed without violating the procedu. e. The "BH train pump was subsequently tested on July 10, 1987 and determined to be operable without meeting T.S. 4.6.2. l.b.

As corrective action, UAU train pump tests were verified to have been performed correctly, and the Unit procedure was revised to ensure proper 1 verification of T.S. 4.6.2.l.b. No similar events have been identified.

8801110406 880105 PDR *DOCK 05000528 cE~

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NRC Ferns 3SSA U.d. NUCLEAR REOULA'TORY COMMISSION id@3 I LlCENSEE EVENT REPORT HLER) TEXT CONTINUATlON APPROVEO OMd NO. 3I50&104 EXPIREd: d/31/dd FACILITY NAME III OOCKET NUMEER l2) LER NI/MSER Id) ~ AOE I31 SEQVENTI*L IISV IS N YEAR NVM E/I <w NVM IO S/l Palo Verde Unit 1 o s o o o 528 8 7 02 7 0 0 0 2 OF 0 4 TEXT //1 /Par SPPCS il /Shuns VPP /hhI/iiVM/HRCAnII30EA'Pl I I TI At approximately 0947 HST on December 7, 1987, with Palo Yerde Unit 1 in Node 5 (COLD SHUTDOWN), it was discovered that Unit 1 had entered Node 4 (HOT SHUTDOWN) at approximately 0234 HST on July 28, 1987 without meeting the surveillance requirements for the containment spray system (BE) UB" train pump (P) as specified in Technical Specification 4.6.2.1.b.

Technical Specification (T.S.) 4.6.2.1.b requires that each containment spray system be demonstrated operable by verifying that each containment spray pump develops an indicated differential pressure of greater than or equal to 257 psid, at greater than or equal to the minimum allowab'te recirculation flowrate, when tested pursuant to T.S. 4.0.5.

Technical Specification 4.0.5 specifies surveillance requirements for inservice inspection and testing in accordance with the applicable requirements of Section XI.of the ASHE Boiler and Pressure Yesse1 Code.

Section XI requires that an inservice test be run on each pump nominally every 3 months during normal plant operations, and recommends that this test frequency be maintained during shutdown periods if this can reasonably be accomplished.

This event was discovered by an individual (utility, licensed) while conducting a review of an approved revisiotl to the Unit 1 containment spray pump operability test procedure, prior to making similar changes in the corresponding Unit 2 and 3 procedures. The surveillance test specified in T.S. 4.6.2.1.b requires the pump to be tested in recirculation mode, however, the Section XI requirements can be met with the pump operating in other operational configurations. The Unit 1 test procedure had been revised, effective July 8, 1987, to permit Section XI testing of the containment spray UB" train pump to be performed in shutdown cooling mode.

On July 6, 1987 an engineering evaluation was performed to establish additional sets of reference values for Section XI testing of the containment spray pumps other than those specified in T.S. 4.6.2.l.b. This evaluation established acceptance criteria for testing the pumps with full flowrate during shutdown cooling, in lieu of the recirculation flowrate, thus permitting Section XI testing to be conducted for a containment spray system pump when in service for shutdown cooling. This evaluation established a reference differential pressure of 217 and 211 psid for the "A" and "B" train containment spray pumps, respectively, with full flowrate conditions. The evaluation specified, however, that additional testing in the recirculation mode was required to comply with the requirements of T.S. 3.6.2.1.

The revision incorporated into the Unit procedure included the values 1

specified in T.S. 4.6.2.l.b in addition to the values provided in the engineering evaluation. The procedure also contained the instructions necessary to conduct the test with the pump in either the recirculation mode or the shutdown cooling mode, 4/IC IOIIM SSA ld S3>

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NRC Form 34SA U.S. NUCLEAR REOULATORY COMMISSION (0431 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OQB NO. 3I50&104 EXPIRKSI SI3II FACILITY NAME III OOCKET NUMBER ISI LER NUMBER ISI ~ AOE ISI YEAR k>'F> SSOUSNT>AL NUM S>l 4

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o>> RFOOo'>ol HIIC %%dm> DNA'rI lltl osooo528 87 02 7 0 0, 0 4oF 0 4 There were no structures, systems or components other than those discussed above that were inoperable at the start of the event that contributed to the, event. There were no automatically or manually initiated safety system responses. There were no unusual characteristics of the work location that contributed to the event. Based upon the above discussion, and the fact that the containment spray UAR train was always operable, this event had no safety consequences.

While other events have been identified (e.g., Unit 1 LfR 86-29-00 and Unit 2 LER 86-16-00) in which a surveillance test was incorrectly performed due to a procedural deficiency, these event did not involve the root cause described above and are not considered similar events.

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0 Artzona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 192-00330-JGM/JEH/KCP January 5, 1988 NRC Document Control Desk NucIear Regu1atory Commission Washington, D.C. 20555

Subject:

Pa1o Verde Nuc1ear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528 Licensee Event Report 87-027-00 Fi1e: 88-020-404 Attached p1ease find Licensee Event Report (LER) No. 87-027-00 submitted pursuant to 10CFR 50.73. In accordance with 10CFR prepared and herewith forwarding a copy of the LER to the Regiona1 50.73(d), we are Region V office. Administrator of the If you have any questions, p1ease contact J. E. Ma1ik, (Acting) Comp1iance Lead at (602) 393-3527.

Very truIy yours,

~.c.4 J. G. Haynes Vice President Nuc1ear Production JGM/JEM/KCP/kj Attachment cc: 0. H. DeHicheIe (a11 w/a)

E. E. Van Brunt, Jr.

J. B. Hartin J. R. Ba11 R. C. Sorenson E. A. Licitra A. C. Gehr INPO Records Center

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