ML18022A540

LER 87-029-01:on 870428,engineer Determined That Snubber Found Damaged on 870422 Per Required Action of Tech Spec. Snubber Damaged Due to Water Hammer Occurring When Valve Isolated.Snubber replaced.W/870731 Ltr

ML18022A540
Person / Time
Site:	Harris
Issue date:	07/31/1987
From:	Tibbitts D, Watson R CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HO-870478-(O), LER-87-029, LER-87-29, NUDOCS 8708050048
Download: ML18022A540 (5)

Text

R ULA RY INFORMATION DISTR JTI . SYSTEM (RIDS)

ACCESSION NBR: 8708050048 DOC. DATE: 87/07/31 NOTARIZED: NO DOCKET FACIL: 50-400 Shearon Harris Nuclear Poeer Planti Unit }i Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION TIBBITTSi D. L. Carolina Power ~4 Light Co.

WATSON'. A. Car o l ina P oeer 5 Lig h t Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-029-0}: on 870428i engineer determined that snubber found damaged on 870422 required action per Tech Spec 3. 7. 8.

Snubber damaged due to eater hammer occurring chen valve isolated. Snubber replaced. W/870731 ltr.

DISTRIBUTlON CODE: IE22D COPIES RECEIVED: LTR l Incident ENCL Rpti

/ SIZE:

etc.

TITLE: 50. 73 Licensee Event Report (LER)i NOTES: Application for permit renewal filed. 05000400 RECIPIENT COP I ES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1

'BUCKLEY'S B 1 1 INTERNAL: ACRS MlCHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 DEDRO } } NRR/DEBT/*DE 1 0 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 NRR/DEST/ELB 1 1 NRR/DEST/ I CSB 1 1 NRR/DEST/MEB 1 NRR/DEST/MTB NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB }. }

NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 1 NRR/DREP/RAB 1 1 NRR/DREP/RPB 2 2 NRR M* RB 1 1 NRR/PMAS/PTSB 1 1 02 1 1 RES DEPY GI 1 RES TELFORDi J } RES/DE/EIB 1 1 RGN2 FILE 01 1 }

EXTERNAL: EGSQ GROHa M 5 5 H ST LOBBY W RD 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS' 1 1 NSIC MAYSi Q 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 43

NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION (94)3) APPROVED OMB NO. 31604101 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

DOCKET NUMBER l2) PAGE 3 FACILITY NAME (1)

Shearon Harris Unit 1 0 5 0 0 0 1 OF TITLE (4)

Steam Generator B'Lowdown .Piping Snubber 'Ino erable EVENT DATE (6) LER NUMBER (6) REPOAT DATE (7) OTHER FACILITIES INVOLVED (8)

YEAR >+~ SEQUENTIAL REVISION MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S)

MONTH OAY YEAR 4)>>A NUMBER NUMBER 0 5 0 0 0 0 4 2 8 8 7 7 0 2 9 0 1 0 7 3 1 8 7 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T O THE REQUIREMENTS OF 10 CFR ()I (Checir one or more of rhe follo<lnp) (11 OPERATING MODE (8) 20A02(B) 20.405(c) 50.73( ~ ) l2)(NI 73.71(B)

POWER 20A05( ~ ) (Ill)i ~ 50.38(cl(ll 60.73( ~ l(2)lr) 73.71(cl ll)00 60.73(s)(2)(r5) OTHER (Specify ln Ab(rrect 1 0 0 20.405(s) 60.38(c) (2) below enrf ln Terr r, Nft C Form 20A06(s l(1) (ii)l 50.73(s) (2)(I) 60,73( ~ ) (2) (rill)(Al 366A) 44M.

4. 20A05(s) ll)(irl 50.73(el(2) liil NI 73(e) (2)(rliil(BI 20A05(sill ) le ) 50.73(s I (2) (I i)) 60.73( ~ ) (2) (4)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NVMBFR AREA CODE Dean L. Tibbitts Director Regulatory Compliance 91 936 2- 271 8 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)

MANUFAC. REPORTABLE '? MANUFAC. EPORTABLE COMPONENT CAUSE SYSTEM COMPONENT TVRER TO NPRDS ELIS<: CAUSE SYSTEM TURER TO NPRDS I??I P... AN.4 Srr(SI SUPPLEMENTAL REPOAT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE (16)

YES flfyer, complete EXPECTED Stf&kf(SSIOhf DATE( NO ABSTRACT (Limit to (400 rpecer, l.e., epprorrlmetefy fifteen rlnple rpece typewritten liner( l18)

On April 22, 1987, with the plant in Mode 1 at 100% power level a snubber was discovered damaged on a steam generator blowdown system'ipe in the Reactor Auxiliary Building. Action was initiated to repair the snubber, and Technical Specification 3.7.8, SNUBBERS, was reviewed for required actions. A decision was made by shift operations personnel and subsequently confirmed by plant management that Specification 3.7.8 was not applicable to this snubber based on the non-safety significance of the attached system and the location of the snubber and the respective piping relative to safety related equipment.

Upon further review, it was determined on April 28 that the snubber in question was covered by Specification 3.7.8 and that action under this specification was required. The snubber was replaced on April 28 and, an engineering evaluation was conducted to verify that the out of service snubber did not result in unacceptable damage to the piping.

8708050048 870731 PDR ADDCK 05000400 S PDR NRC Form 388 194)3 I

NRC Form 366A US. NUCLEAR REGULATORY COMMISSION (883)

LIC NSEE EVENT REPORT (LER) TEXT CONTINUA ION APPIIOVEO OM8 NO. 3150&104 EXPIRES: 8/31 /88 FACILITYNAME I'l OOCKET NUMBER l2) LER NUMSER )6) PAGE (3)

SSOUENTIAL REYISION Shearon Harris - Unit 1 YEAR NUMSSR NUMBER TEXT CPRKss ~ Er rsqrrked. ow abblbneI IPRC IYrrrrr 38549I ) IT) 0 5 0 0 0 4 0 0 8 7 0 2 9 0 1 0 2 OF 0 3 DESCRIPTION On April 22, 1987, while the plant was operating in Mode 1 at 100% power level a snubber was found damaged on the Steam Generator Blowdown System piping from Steam Generator 1A. The snubber was located inside the Reactor Auxiliary Building. A work request was initiated to repair the snubber. The on"shift operations personnel reviewed Technical Specification 3.7.8, SNUBBERS, and determined that this specification was not applicable because the attached system had no safety function, and was not covered by Technical Specifications.

Work was begun on April 23 to correct the situation. In addition to the damaged snubber, two broken pipe supports and apparent pipe displacement were discovered. The supports were replaced in the evening of April 23. The snubber could not be replaced due to inadequate clearances resulting from the pipe displacement.

On April 27, engineers from the In-Service Inspection group, who had become involved in the repair, informed the Manager Operations that the snubber did require action under Technical Specification 3.7.8, based on their understanding of the specification and its bases. Operations and Regulatory Compliance reviewed the situation and determined that Specification 3.7.8 did not appl,y based on the non-safety significance of the attached system, on the location of the affected piping relative to safety-related systems, and on the location of the affected piping relative to the containment isolation valve for that particular blowdown line.

The Quality Assurance department became aware of the situation and issued a Non-Conformance Report on April 28. This led to a more detailed review by Regulatory Compliance of the particular snubber and the Technical Specification bases for Specification 3.7.8., as well as the design bases for the steam generator blowdown system. It was determined that Specification 3.7.8 did in fact apply to the snubber and therefore the plant had not met the requirements of the Technical Specifications to restore the snubber within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and to evaluate the effect on the attached system, or declare the affected system inoperable. However, since the Steam Generator Blowdown System is not covered by a specific specification, declaration of inoperability would require no specific action be taken.

The snubber was replaced on ApT'il 28. An engineering evaluation concluded that the "as-left" condition of the piping was acceptable', this was compI.eted on May 7, 1987.

During the time period in question, steam generator bl.owdown was in service.

The plant was in the applicable modes for which Specification 3.7.8 applies throughout the period; However, during an unrelated outage from May 2 to May 9, the plant entered Mode 4 and steam generator blowdown was secured.

&RC FORM 3SSA o U.S.GPO,1986 0.624 538/455 I94LT)

NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION I94)3l, LICENSEE E ENT REPORT HLER) TEXT CONTINUA lON APPROVED OMB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME Ill DOCKET NUMBER I2) LER NUMBER (6) PAGE 13) 8<<.'<<I SEQUENTIAL g+'EVISION YEAR NVM8f R <<...4 NVMSER Shearon Harris Unit 1 o s o o oA 00 87 029 0 1 0 30F TEXT ///mes 4/Nof /4 nocked, INE EEI/onf/NRC hvm 3SLE'4/ )IT)

CAUSE The design of the Steam Generator Blowdown piping is safety-related because of FSAR commitments made to support the analysis for high energy piping breaks outside the reactor containment building. Having a Seismic Category I design limits the number of postulated piping breaks to consider as well as relaxing the requirements for pipe whip restraints. Due to the safety-related design of the pipe and the consequences of blowdown line ruptures in the Reactor Auxiliary Building, snubbers in the Steam Generator Blowdown System are subject to Specification 3.7.8. This information is not stated in the Technical. Specification nor in the bases section, nor is it clear based on the action statement of the specification.

Personnel and managers involved in the assessment of the snubber were also not aware of its significance to pipe break analyses. Becau'se a Technical Specification Limiting Condition for Operation was not entered, immediate management attention was not given to the situation and the snubber repair did not proceed within the time allowed by the specification.

The cause of the blowdown piping displacement and snubber damage was determined to be water hammer occurring when the isolation valve for the line from containment is opened.

ANALYSIS This event is being reported per 10CFR50.73 (a) (2) (i) (B) as a violation of the Technical Specifications. The plant design depends on the integrity of steam generator blowdown piping to satisfy high energy line break analyses requirements. Technical Specifications limit the allowed time during which the condition of the piping can be indeterminate prior to requiring action to be taken. This time limit, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, was exceeded.

There were no safety consequences as a result of this event since the blowdown piping was not damaged to the point where leakage occurred.

CORRECTIVE ACTION The probability of water hammer in the steam generator bl.owdown piping will be reduced by increasing the open stroke time of the isolation valve. This change will. be completed in conjunction with the next scheduled outage, which is currently pLanned for the Last quarter of 1987.

The requirements for action under Specification 3.7.8 have been addressed in a Technical Specification Interpretation document.

NRC I'ORM SSEA *U,S.GPO'11986 0.624 638/455 1983)

0 ~

CML Carolina Power,& Light Company 4

HARRIS NUCLEAR PROJECT P.O. Box 165 New Hill, NC 27562 JUI ~i >~01 File Number. SHF/10-13510C Letter Number.'O-870478 (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 87-029-01 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 reportable occurrence and is in accordance with the format set forth in NUREG-1022, September, 1983.

Revision 1 to LER 87-029-00 is being submitted to change the completion date for the corrective action. LER 87-029-00 stated that the change to the open stroke time of the isolation valve will be completed by July 31, 1987. Needle valves have been installed to accomplish this; but due to operational considerations, the steam generator blowdown system cannot currently be isolated as needed to adjust the stroke times of the valves. Therefore, the corrective action will now be completed in conjunction with the next scheduled outage.

Very truly yours, Zcpi~rw~~

R. A. Watson Vice President Harris Nuclear Project ONH'RAW'ddl Enclosure cc.'Mr. B. Buckley (NRR)

Dr. J. Nelson Grace (NRC RII)

Mr. G. Maxwell (NRC SHNPP) /peil>

MEM/HO-8704780/PAGE 1/Osl