ML17303A393

LER 87-006-00:on 870307,during Surveillance Test,Limiting Condition for Operation 3.0.3 Entered When Tech Spec 3/4.6.3 Action Statements Could Not Be Met.Caused by Inoperability of Msivs.Tech Spec Change Request submitted.W/870403 Ltr

ML17303A393
Person / Time
Site:	Palo Verde
Issue date:	04/03/1987
From:	Bradish T, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
192-00184-JGH-T, 192-184-JGH-T, LER-87-006-01, LER-87-6-1, NUDOCS 8704130229
Download: ML17303A393 (6)

Text

REGULATOR NFORMATION DISTRIBUTION S EM (RIDS) 4J '

ACCE SCION NBR: 8704130229 DOC. DATE: 87/04/03 NOTAR I ZED: NO DOCKET FAG IL: STN-50-529 Palo Verde Nuclear Stations t Uni 2> Arizona Pub 1 i 05000529 AUTH. NAME AUTHOR AFF I LIATION BRADISH, T. R. Arizona Nuclear Power Prospect (formerly Arizona Public Serv HAYNES> J. G Arizona Nuclear Power Pro Ject (formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILIATION SUB JECT: LER 87-006-00: on 870307'u> ing surveillance test, limiting condition For operation 3. 0. 3 entered when Tech Spec 3/4. h. 3 action statements could not be met. Caused bg inoperability of MSIVs. Tech Spec change request submitted. 8/870403 itr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: 50. 73 Licensee Event Report (LER) i Incident Rpt> etc.

NOTES: Standardi zed plant. M. Davisi NRR: fCg. 05000529 REC IP I ENT COPIES RECIPIENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 f LICITRA> E ,1 1 DAVIS' 1 INTERNAL: ACRS MICHELSON 1 1 *CRS MOELLER 1 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TAPB 1 1 NRR/ADT 1 1 ERR/DEST/ADE 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB } 1 NRR/DEST/ ICSB 1 1 NRR/DEBT/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 ERR/Dl PG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB 1 1 NRR/DREP/EPB 1 ERR/DREP/RAB 1 1 NRR/PMAS/ ILRB 1 NRR/PMAS/PTSB 1 1 E 02 1 1 RES SPEISs T 1 1 RGN FILE 01 1 1 EXTERNAL: EG8(Q GROH> M 5 5 H ST LOBBY NARD 1 1 LPDR 1 1 NRC PDR 1 1 NSI C HARRIS J 1 1 NSIC MAYST G 1 1 NOTES:

TOTAL NUMBER OF COPIES REQUIRED: LT IR 43 ENCL 41

0 NRC Form 355 U.S. NUCLEAR REOULATORY COMMISSION (9.53)

APPAOVED OMS NO 31504)104 LICENSEE EVENT REPORT {LER) EXPIAES: 5/31/55 FACILITY NAME II) DOCKET NUMSER 12) PA E 3 Palo Verde Unit 2 0 5 0 0 0 5 2 9 1 OFO TITLE Iel Entr into LCO 3.0.3 Due to Ino erable Main Steam Isolation Valves EVENT DATE (5I LEA NVMSER Ie) AEPORT DATE It) OTHER FACILI'TIES INVOLVED Ie)

MONTH DAY YEAR YEAR;i% seovcNTIAL NVMSSR Il4 VIS lON Sor NUMSER Mo~' OAY YE'AR FACILITYNAMES DOCKET NVMSER(SI N/A o 5 o o o 0 3 0 7 8 7 8 7 0 0 6 0 04 03 87 N A 0 5 0 0 0 THIS REPOR'7 IS SUSMITTED PURSUANT 7 0 THE REOUIREMENTS OF 10 CFR ()I ICnrc>> one or morr o/ thr Ioriowinp/ l'11 OPEAATINO MODE ( ~ I 20.402(el 20A05(cl 50.73(el l1) llvl 73.71(III POWER 20.405( ~ ) (1)(ll 50.35 (c) (I ) 50.73(e I (2 I (vl 73.71(cl

=

LEYEL 0 0 0 20.405( ~ l(I)le) 50.35(cl(2) 50.73( ~ l(1)(vel oTHER Isprcliy in Aottrrct trerow rodin Text. /tRC Form

'~err (Tgj%ip$ j/E+~ypq~vc 20.405( ~ l(1) (Ail 50.7 3 I ~ I (2)(O 50.73(el(2) (vSI I(A) 3PEAI 20,405( ~ Ill ) 0 v) 50.73(e) 11)(4( 50.73 Ie) (2)(el 4 II 5 I 20.405 (I I II I (vl 50.73 le l(2((SI) 50.7 3(el (1 I Ix )

LICENSEE CON1'ACT FOA THIS I.ER (11)

NAME TELEPHONE NUMSEA AREA CODE Thomas RE Bradish, Compliance Supervisor (Ext. 6936) 602 932 0 0 COMPLETE ONE LINE FOR EACH COMPONEN'T FAILVAE DESCAISED IN THIS REPORT (13)

MANVFA(r EPORTASLE MANVFAC.

CAUSE SYSTEM COMPONENT TVREA TO NPADS

.~N@eR+.A,. vga~ CAUSE SYSTEM COMIONENT TUAEA KP~kY ij'@+jjrrlÃ

rCCXCv.'4YA&i~~~ti:

SUPP(,EMEN'TAL AEPORT EXPECTED (I ~ ) MONTH OAY YEAR EXPECTED SUSMISSION DATE (15)

YES Ii/ yn. comp/err EXPECTED SVdM/SSIDH DATE/ NO ASSTAACT IL/mrt to te00 Iprcn, I r.. epproximnriy A/tern tinpir Ipecr typrwrrttrn /inn/ (Ie)

At 1927 HST on March 7, 1987, Palo Verde Unit 2 was in Mode 3 (HVZ STANDBY) with an, average Reactor Coolant System temperature of 564 deg'rees F.

As a result of corrective maintenance conducted on all four Hain Steam Isolation Valves (MSIVs) during the recent outage, they were secured in their closed position until they could be tested and declared operable in Mode 3 when normal operating steam pressure and temperature for the secondary side could be achieved. Control room operators (utility-licensed) were conducting an approved Surveillance Test (ST) for the MSIVs when the Technical Specification (T.S.) Limiting Condition for Operation (LCO) 3.0.3 was entered when T.S. 3/4.6.3 ACTION Statements could not be met. LCO 3.0.3 was entered and exited ll times when the MSIVs .were stroked open and closed as part of the ST.

The cause for the KO 3.0.3 entries is that the system design (1 HSIV per steam line) does not allow the T.S. 3/4.6.3 ACTION Statements to be met inoperable.

if the MSIV is As corrective action, a T.S. change has been previously submitted to the NRC which would revise T.S. Table 3.6-1 to remove the four MSIVs from the requirements of T.S. 3/4.6.3, "Containment Isolation Valves". This change has been incorporated into the Unit 3 T.S. Incorporation into Units 1 and 2 T.S. is expected soon.

S704130229 870403 PDR ADQCK 05000529 8 PDR NRC Ierm See

NRC FOrm 34$ A V.s. NUCLEAR REQVLATORY COMM($$ IQN 1943 I LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROYEO OMS NO 3(EQ~IQo EXPIRES: 4(3((44 FACILITY NAME ((I OOCKET NVMEER l3(

LER NVMEER (4) PACE (3I

~v, FEQvErrTIAL ..go oovolorr

.+>? NUM ER ~ +~ HVMOTO Palo Verde Unit TEI(T pl moro oooro u 2

rorroood, ooo orOooror HRC Form 3(((A'ol (IT(

o s o o o 529 8 7 006 00 02oF 0 3 At 1927 MST on March 7, 1987 through 0922 on March 8, 1987, Palo Verde Unit 2 was in Mode 3 (HOZ STANDBY) with an average Reactor Coolant System (AB) temperature of 564 degrees F, when Technical Specification (T.S.) Limiting Condition For Operation (LCO) 3.0.3 was,entered and exited eleven times due to not meeting the ACTION Statements of T.S. 3/4.6.3 "Containment Isolation Valves". The inability to meet the ACTION Statements of T.S. 3/4.6.3 was due to inoperable Main Steam Isolation Valves (HSIV)(SB)(ISV). The events were identified by the Shift Supervisor (utility-licensed) and the total combined duration was approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.

As a result of corrective maintenance conducted on all four MSIVs during the recent outage, the valves were secured in their closed position until they could be tested and declared operable in Mode 3 when nor'mal operating steam pressure and temperature for the secondary side could be achieved. Control Room operators (utility-licensed) were conducting the approved Surveillance Test (ST) 42ST-2SGOl for the HSIVs when LCO 3.0.3 was entered and exited as the MSIVs were stroked open and closed as part of the ST. As the valves are opened they become inoperable until successful completion of the ST.

The cause for the LCO 3.0.3 entries was due to the fact that the system design (1 HSIV per steam line) does not allow T.S. 3/4.6.3, ACTION 1 to be met. The ACTION Statement requires that with one containment isolation valve inoperable, the other isolation valve in the line must be operable. This is not possible with only one MSIV per steam line (no other isolation valve in the line). The following table is a listing of the LCO 3.0.3 entries attributed to the surveillance testing of the MSIVs during plant heatup.

LCO 3 '.3 ENTRY TIME LCO 3.0.3 EXIT TIME REASON FOR LCO 3.0.3 3/7/87 1927 1936 MSIV 170 Opened 1939 1946 I'iSIV 180 Opened 1954 ~

2017 HSIV 171 Opened 2020 2025 MSIV 181 Opened 3/8/87 0043 0118 MSIVs 170, 180 Opened 0124 0203 liSIVs 171, 181 Opened 0205 0255 HSIVs 170, 171, 180 8 181 Opened

"

0305 0400 MSIV 171 Opened 0641 0740 MSIV 171 Opened 0812 0823 MSIV 171 Opened 0857 0922 MSIV 171 Opened voc r Qou 3OOo (9 43<

NRC form SOSA U.S. NUCLEAR REGULATORY COMM/$$ /ON ISSSI LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO 1150 010I EXPIRES S/SI/IXI F AC I L I T Y NAME lI I I DOCKET NUMSER 12)

LER NUMSER 1$ 1 PAGE IS)

YEA/I jCrg SEOVENT/AL 'Sll AEV/SIGN NVMof/I NVM FW Palo Verde Unit TEXT //f rlroro I/loco 2

/I ror/rr/rorL Iroo ddatiirW H/TC Forrrr SISEA2/ II 2) 0 5 0 0 0 5 2 9 8 7 006 00 03 OF 0 3 As corrective action to prevent recurrence, a T.S. change has been previously submitted to the NRC which would revise T.S. Table 3.6-1 to remove the four MSIVs from the requirements of T.S. 3/4.6.3, "Containment'Isolation Valves". The basis for this T.S. change is that T.S. 3/4.7.1.5 specifically provides operability and surveillance requirements for the MSIVs which are consistent with the assumptions of the PVNGS MSIV safety analyses. The T.S. change for Units 1 and 2 was published in the Federal Register on February The recently issued Unit 3 T.S. have incorporated the T.S. change.

ll, 1987 for public comment.

Incorporation into Units 1 and 2 is expected soon.

There were no structures, components, or systems inoperable at the start of the event, other than those previously described, that contributed to the event.

There were no automatically or manually initiated safety system responses. There were no safety limits approached and no fission product barriers were challenged.

The MSIVs were tested satisfactorily and were able to be closed even though they were declared inoperable. Therefore, there was no threat to the health and safety of the public. Should other concerns or information pertinent to this event be discovered, a supplement to this report will be issued.

A similar event describing LCO 3,0.3 entry due to inoperable MSIVs has been previously reported in LER 87-006-00-for Palo Verde Unit 1. The corrective action for that event is the same as described above.

NAG I 0/rM 14OA 10 SSr

Arizona Nuclear Power Project P.o. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 192-00184-JGH/TRB/TJB April 3, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 2 Docket No. STN 50-529 Licensee Event Report 87-006-00 File: 87-020-404

Dear Sirs:

Attached please find Licensee Event Report (LER) No, 87-006-00 prepared and submitted pursuant to 10 CFR 50.73. In accordance with 10 CFR 50.73(d), we are herewith forwarding a copy of the LER to the Regional Administrator of the Region V Office.

If you have any questions, please contact T. RE Bradish, Compliance Supervisor at (602) 932-5300 Ext. 6936.

Very truly yours, "J. G. Haynes Vice President Nuclear Production JGH/TJB/cld Attachment CC: 0. M. DeMichele (all w/a)

E. E. Van Brunt, Jr.

J. B. Martin R. P. Zimmerman R. C. Sorensen E. A. Licitra A. C. Gehr INPO Records Center

1 I

qE