ML18004B795
| ML18004B795 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 04/24/1987 |
| From: | Watson R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| HO-870415-(), HO-870415-(0), HO-870415-(O), NUDOCS 8704300291 | |
| Download: ML18004B795 (5) | |
Text
REGULA INFORMATION DISTRIBUTI STEN (RIDS)
ACCESSION NBR: 8704300 91 DQC. DATE: 87/04/24 NOTARIZED:
NO F*CIL:50-400 Shearon Harris Nuclear PoIJer Plant>
Unit ii Carolina AUTH. NAME AUTHOR AFFILIATION WATSON'. A.
Carolina Power 8< Light Co.
RECIP. NANE RECIPIENT AFFILIATION
'Document Control Branch (Document Control Desk )
SUBJECT:
Forwards rept re challenges to PORVs 8c safety valves tohich occured in 1986. Info provided in lieu of submitting data in 1987 annual rep t.
DISTRISUTIDN CDDE:
IE22D CDPIES RECEIVED: LTR )
- ENCL i SIZE:
TITLE: 50. 73 Licensee Event Report (LER)I Incident Rpti etc.
DOCKET 05000400 NOTES: Application for permit rene'!al fi led.
05000400 RECIPIENT ID CODE/NANE PD2-1 L*
BUCKLEY, B INTERNAL: ACRS NICHELSON AEOD/DOA AEOD/DSP/TPAB NRR/DEBT/ADB NRR/DEST/ELB NRR/DEBT/NEB NRR/DEBT/PBB NRP/DEBT/BQB NR)(/DLPG/GAB NRR/DREP/EPB NRR/DREP/RPB NRR/PNAS/PTBB RES SPEIS, T EXTERNAL:
EQRG QROH, N LPDR NBIC HARRIS, J COPIEB LTTR ENCL 1
1 1
1 1
1 1
1 1
1 0
1 1
1 1
1 1
1 1
1 2
2 1
1 1
1 5
5 1
1 REC IP IENT ID CODE/NAME PD2-1 PD ACRS NOELLER AEOD/DSP/ROAB NRR/DEBT/ADE NRR/DEST/CEB t!RR/DEST/ ICSB NRR/DEBT/MTB NRR/DEST/RSB t!RR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RAB NRR/PNAS/ ILRB R
02 GN2 FILE 01 H ST LOBBY 4IARD NRC PDR NSIC MAYS, G COP IER LTTR ENCL 1
1 1
1 2
2
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1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 TOTAL NUNBER QF COPIES REQUIRED:
LT1R 41 ENCL 39
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Carolina Power 8, Light Company HARRIS NUCLEAR PROJECT P.O.
Box 165 New Hill, NC 27564 APR 24 1987 File Number'SHF/10-10000 Letter Number:
HO-870415 (0)
Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400 LICENSE NO. NPF-63 Gentlemen:
Pursuant to Technical Specification 6.9.1.2c for the Shearon Harris Nuclear Power Plant, Unit No. 1, Carolina Power
& Light Company herewith submits a report of challenges to the pressurizer power-operated relief valves (PORVs) and safety valves which occurred in 1986.
Technical Specification 6.9.1.2c does not require an Annual Report for 1986 since initial criticality was not achieved until January 3,
1987.
- However, the attached information is being provided in lieu of submitting the data in the Annual Report for 1987.
Very truly yours, R. A. Watson Vice President Harris Nuclear Project RAW:MW:skm Enclosure cc:
Dr. J. Nelson Grace (NRC)
Messrs.
G. F. Maxwell (NRC SHNPP)
J.
M. Taylor (NRC) 8 7043002'V 1 87p424 PDR ADOCK 05000400 S
PDR MEM/HO-870415(0)/PAGE 1/Osl
CHALLENGES TO THE PORV's AND SAFETY VALVES A.
On December 3,
- 1986, a low-temperature, over-pressure event occurred while conducting filland venting operations of the Reactor Coolant System.
The cause of the event was due to personnel error aggravated by a procedural deficiency and equipment problems.
The pressurizer Power Operated Relief Valve lifted at its appropriate setpoint to control Reactor Coolant System pressure.
(Special Report dated January 2,
1987)
B.
On December 8,
- 1986, a low-temperature, over-pressure event occurred while the Reactor Coolant System was being operated under solid water conditions.
The cause of the event was due to a failed capacitor in the power supply card for the pressure transmitter for.
the letdown system's pressure control valve (PCV-145).
The pressurizer Power Operated Relief Valve lifted at its appropriate setpoint to control Reactor Coolant System pressure.
(Special Report dated January 2,
1987)
C.
On December 29,
- 1986, a over-pressure event occurred during preparation for Power Ascension Test "Rod Drop Test No Flow Condition".
The cause of the event was due to a pressure transient caused by starting an idle Reactor Coolant Pump.
The pressurizer Power Operated Relief Valve lifted at its appropriate setpoint to control Reactor Coolant System pressure.
MEM/HO-870415(0)/PAGE 3/OS1
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