ML17223A675

LER 90-006-00:on 900426,surveillance Not Performed on Control Element Assemblies (Cea).Caused by Procedural Deficiency.Reactor Startup Procedure Revised to Require Performance of Addl CEA surveillances.W/900526 Ltr

ML17223A675
Person / Time
Site:	Saint Lucie
Issue date:	05/26/1990
From:	Sager D, Weeks J FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-90-192, LER-90-006-01, LER-90-6-1, NUDOCS 9006040243
Download: ML17223A675 (7)

Text

ACCELERATED DISTRIBUTION DEMONS'.TION SYSTEM REGULATORY ZNFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9006040243 DOC ~ DATE: 90/05/26 NOTARIZED: NO DOCKET FACZL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION WEEKS,J.W. Florida Power & Light Co.

SAGER,D.A. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 90-006-00:on 900426,missed surveillance on control element assemblies due to procedural deficiency.

W/9 DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50,73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES'ECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 DEDRO 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB SD 1 1 NRR/DST/S ICB 7 E 1 1 PLBSD1 1 1 NRR/DST/SRXB SE 1 1 02 1 1 RES/DS IR/EI B 1 1 RGN2 FILE 01 1 1 EXTERNAL EG&G STUART i V ~ A 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS, G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

h PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUZRED: LTTR 36 ENCL 36

P 0 So~ )-"r,'00 Juno Beach FL 334."8.G-'20 APL L-90-192 10 CFR 50.73 May 26, 1990 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:

Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 90-06 Date of Event: April 26, 1990 Missed Surveillance on Control Element Assemblies Due To Procedural Deficienc The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.

Very truly yours, ON D. A. S

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er Vice sident St. c e Plant DAS:RAD:kw Attachment cc: Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant DAS/PSL N166 pre'V

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)vest sss IIM APPROVED OMS NO. 31504104 LICENSEE EVENT REPORT (LER) EXPIRES 8/31/85 FACII.ITYNAME (1) DOCKET NUMBER (2 PAGE 3 St. Lucie Unit 1 0 500033 51OFO 3 TITLE (4)

Missed Surveillance on Control Element Assemblies Due to Procedural Deficiency EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR IAL I MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(s)

NUMBER NUMBER St. Lucie Unit 2 0 500038 9 0 4 2 6 9 0 9 0 0 0 6 0 0 0 5 9 0 N/A THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR OPERATING Check one or more of the followin 11 MODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)

POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)

LEVEL (10) 0 3 0 20.405(a) (1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER (Specifyin Abstract 20.405(a)(1)(iii) X 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) below and /n Text 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) NRC Form 366A) 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (12)

NAME H N M AREA CODE J. W. Weeks, Shift Technical Advisor 4 0 7 465-3 550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE sYSTEM COMPONENT MANUFAC- TURER REPORTABLE TO NPRDS CAUSE SYSTFM COMPONFNT MANUFAC- TURER REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED N AY Y A SUBMISSION YES (Ifyes, complete EXPECTED SUBMISSION DATE) NO DATE (15)

ABSTRACT (Limit to 1400 spaces. i.e. approximately fifteen single-space typewritten lines)(16)

On April 26, 1990, with Unit 1 at 30% power and holding for Steam Generator Chemistry, a Quality Control Supervisor discovered that Technical Specification surveillances 4.1.3.1.2 (Unit 1 only) and 4.1.3.1.3 were not being performed each time the reactor was started up. These surveillances functionally test the Control Element Assembly (CEA) Block Circuits. By not performing these surveillances on each startup it is possible to exceed the 31 day maximum time allowed between sutveillances.

The root cause of the event is due to a procedural deficiency. The Reactor Startup procedure (OP-1/2-0030122) requires the performance of Technical Specification surveillances 4.1.3.1.1 and 4.1.3.1.4, which tests other portions of the Block Circuit, but does not require the performance of 4.1.3.1.2 (Unit 1 only) and 4.1.3.1.3. The omission of requiring that these surveillances be done led to exceeding the 31 day surveillance requirement. A review of the Unit 2 Reactor Startup procedure revealed a similar deficiency in that it did not ensure that the CEA Block Circuit surveillance had been performed within 31 days.

Corrective actions taken were to revise the Reactor Startup procedure for both units to require the additional Control Element Assembly (CEA) Block Circuit sutveillances be performed on each reactor startup, unless performed within the previous 31 days.

0 I PL U.S. NUCLEAR REGULATORY COMMISSION 1'Kfe Xl APPROVED OMB NO. 01500104 II451 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION EXPIRES 8/81/85 FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR SEQUQTIAL RF Vl/IPN N

St. Lucie Unit 1 0 500 033 5 9 0 0 0 6 0 0 0 2 0 3 TEXT (It more space is required, use additional NRC Form 3S6A's)(17)

On April 26, 1990, while Unit 1 was in Mode 1 at 30% power and holding tor Steam Generator Chemistry, it was discovered by a Quality Control Supervisor that Control Element Assembly (CEA)

(EIIS:AA) Block Circuit Technical Specification surveillances 4.1.3.1.2 and 4.1.3.1.3 had not been performed in the previous 31 days. These surveillances functionally test the CEA Block Circuit. By not performing these sutveillances during every startup, it allows for the possibility of the 31 day maximum testing frequency to be exceeded.

A review of the Unit 2 Reactor Startup procedure revealed a similar deficiency in that it did not ensure that the CEA Block circuit surveillance had been performed within 31 days. These surveillances are normally scheduled to be performed on the tourth Thursday ot each month (third Thursday for Unit 2).

If an outage occurs which prevents the performance of these surveillances, the next surveillance is performed on the fourth Thursday (third Thursday for Unit 2) after the startup. A span of up to 60 days in Modes 1 or 2 without the performance of these surveillances could result.

The root cause of the event is due to procedural deficiency. The Reactor Startup procedure (OP-0030122) includes CEA overlap testing which performs 4.1.3.1.1 and 4.1.3.1.4 that tests other portions of the Block Circuit. Utility personnel had mistakenly thought that the Block Circuit was being tully tested in the performance ot this step ot the Reactor Startup procedure.

Interpretation regarding the boundaries of the block circuit led to the omission of the surveillances from the Reactor Startup procedure originally, and contributed to the reason that the omission had not been discovered until now. The surveillances performed atter refueling outages were thought to cover these requirements. However, upon further research it was determined that only a portion of the Block Circuit was being tested. Therefore, it is necessary to have included the normal 31 day surveillance test in the Reactor Startup procedure to ensure the time restraint was not exceeded.

Subsequent Block Circuit tests were satisfactory, indicating that the CEA Block Circuit was operable.

All previous Block Circuit tests were performed satisfactorily. Therefore the health and safety of the public were not affected by this event.

This event is reportable to the NRC under 10CFR50.73(a)(2)(i)(B) as any operation or condition prohibited by the plant's Technical Specification.

SFLF~ U.S. NUCLEAR REGULATORY COMMISSION (S SF(CF~

APPROVEO 0MB NO. 31504104 SSS ((45( LICENSEE EVENT REPORT (LER) TEXT CONTINUATION EXPIRES S/3l/85 FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

YEAR EQUENTIAL RF VISIO NUMBER NUMBER St. Lucie Unit 1 05000335 9 0" 0 0 6 0 0 0 3 0 3 TEXT (Ifmore spaceis required, use additional NRC Form 366A's)(17)

V TI On April 26, 1990, the surveillances were performed satisfactorily.

The surveillance test procedure that performs the requirements of Technical Specifications 4.1.3.1.2 and 4.1.3.1.3 were added to the Reactor Startup procedure (OP-1-0030122) to be performed at each reactor startup.

St. Lucie Unit 2 Technical Specifications and procedures were checked for the same requirements. It was determined that the same situation existed on Unit 2, therefore it is being included in this LER.

The Unit 2 Reactor Startup procedure (OP 2-0030122) will be revised the same zs for Unit 1.

None Other events at St. Lucie involving missed Technical Specification surveillances due to procedural errors:

LER 335-83-016 LER 335-81-006 LER 335-78-008 LER 335-76-029 SFL FeCaeW S( SSI(; Fess SSS (SMI