SNRC-1431, Shoreham Nuclear Power Station Annual Operating Rept,Jan- Dec 1987
| ML20196E336 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/31/1987 |
| From: | Leonard J, Steiger W LONG ISLAND LIGHTING CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| SNRC-1431, NUDOCS 8803010041 | |
| Download: ML20196E336 (10) | |
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LONG ISLAND LIGHTING COMPANY SHOREHAM F'JCLEAR POWER STATION ANNUAL OPERATING REPORT l
JANUARY 1, 1987 THROUGH DECEMBER 31, 1987 r
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ye Approved Date f
W. E.
Steiger Plant Manager i
8803010041 871231 r
PDR ADOCK 05000322 a
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TABLE OF CONTENTS 1.0 Emergency Core Cooling (ECC) System Outages 2.0 Personnel and Man-Rem by Work and Job Function l
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l.0 Emergency Core Cooling (ECC) Systems Outage From January 1, 1987 to December 31, 1987 there were 45 limiting conditions for operations (LCO's) for the ECC Systems.
Eleven (11) of the 45 LCO's were actual requirements per-Technical Specifications.
The remaining 34 were for tracking.
At Shoreham, an LCO is categorized as a "tracking LCo" if the technical specification LCO occurred while the reactor was in an operational mode other than that-for which the LCO is applicable.
Tracking LCo's are none-the-less important because they provide assurance that operability will be restored prior to entering the applicable operational mode.
Of the 11 actual LCO's the breakdown is as follows:
1 is for Ell, Low Pressure Coolant Injection (LPCI) 5 are for E21, Core Spray (CS) 1 is for Ell and E21 combined, LPCI and CS 4
are for E41, High Pressure Coolant Injection (HPCI)
These 11 actual LCO's are detailed in Table 1-1 indicating for each component by system, the outage dates, duration, and the reason for the outage.
Four (4) of the 11 actual LCO's placed the system inoperable due to surveillance testing, and 7 were due to equipment failure.
The corrective action for the 7 LCO's due to equipment failure are described below:
LCO A87-437 Problem description:
During QCD surveillance inspection two RHR snubbers were found faulty.
Evaluation under Engineering and Design Coordination Report (E&DCR) H-659A attributed the failure to line voids, which resulted in wsterhammer.
Corrective action:
(1) Snubber damage has been temporarily repaired; (2) Installation of electrical interlocks to prohibit the RHR rump suction selves and Reactor Pressure Vessel (RPV) suction valves from being open at the same time; (3) piping and fitting inspection for material failure; (4) performance of a pressure decay test of the shutdown cooling suction header; (5) procedure change to preclude possible voiding of the shutdown cooling suction header; (6) performance of a full flow test of the A and C RHR pumps; and (7) initiation of a special snubber inspection program.
LCO A87-365 Problem description:
Replaced 4KV breaker for loop B Core Spray pump for lug crimp inspection.
Corrective action:
During a QC inspection of lugs it was suspected that the breakers for the Core Spray "B" pump had incorrect AMP terminals in conjunction with No. 14 wire.
Core Spay loop B was taken out of service to replace the breaker.
Upon further review of the breaker lugs it was determined that the AMP terminals were the correct size.
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LCO A87-32 Problem description:
During pressurization of the Drywell/
Reactor Pressure Vessel for the type A intergrated Leak Rate Test, the loop A ECCS low level instrumentation became inoperable when the "A" RPV reference leg partially drained
'due to a leak from a level transmitter.
Corrective action:
Leak from vent valve on level transmitter was repaired.
LCO A87-218 Problem description:
HPCI equipment area (elevation 63')
temperature reading high.
Temperature switch was found out of calibration.
Corrective action:
Recalibrated area temperature switch.
LCO A07-225 Problem description:
During surveillance testing the required flow and pressure could not be obtained for the HPCI turbine at the rated Reactor pressure of 920 psig.
Corrective action:
Vented e.ir out of both legs of flow transmitter FT-003, checked calibration, and adjusted high limit on flow controller FC-003 to 4.8 VDC per G.E.
recommendation.
l LCO A87-228 Problem description:
Steam leak on the HPCI turbine drain found during pc formance of leakage reduction program inspection.
Corrective action:
Reinctalled two new flexitalic gaskets on orifice assembly LCO A87-236 Problem description:
During surveillance testing of HPCI test return to Condensate Storage Tank (CST) valves, valves would not stroke full closed against rated pressure and flow.
Corrective action:
Maintenance Work Request (MWR) was initiated for HPCI test return to CST valves, E41*MOV-037 and 038 to disassemble and rework as required.
The disc in E41*MOV-037 has been modified.
The gearing for the motor operator for E41*MOV-d38 will be changed.
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TABLE 1-1 Sheet:1 of 2 DATE OUT DATE RE*IUIEED DURATION SYSTD1 00TONENT IfD #
OF SERVICE
'IO SERVICE DAYS /IfRS.
REASON OUP Ell IICI, IOOP A&B A87-437 12/11/87 12/11/87 0 /5.5*
Pipe support found inop during inspection E21 Core Spray, Loop A&B A87-43 1/27/87 1/27/87 0 /6.6 Surveillance testing on the min flow valve instrumentation.
E21 Core Spray, Imp B A87-181 5/8/87 5/12/87 4 /19.5 Suppression Pool water level reduced, initiated special surveillance to monitor CST water level.
E21 Core Spray,Icop B A87-343 8/21/87 8/21/87 0 /1.2 Surveillance testing for SP 44.203.09, Injection valve permissive E21 Core Spray,Icop B A87-359b 9/18/87 9/18/87 0 /3.2 Surveillance testing, differential pressure calibration for Injection valve E21 Core Spray, Loop B A87-365 10/2/87 10/2/87 0 /6.3 Repla d b'reaker for "B" Core Spray Punp for inspection of lug crinps Ell /E21 Core Spray & LPCI A87-32 1/20/87 1/23/87 3 /4 During pressurization of drywell for the type A test-(ILRT), a leak was found on level transmitter causing the
'A' RPV water level reference leg to partially drain.
E41 IIPCI A87-218 5/4/87 5/27/87 0 /9.5 El 63 feet Reactor Bldg.
Equi xnent Area area tenperature readirx3 high I
E41 IIPCI A87-225 5/29/87 5/29/87 0/10.1 Required flow and pressure Turbine not obtained with Reactor pressure at 920 psig.
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TABIE 1-1 Sheet 2 of 2.
DATE OUT DATE RINURNED DURATION SYSTIM CNP0 TENT 100 5 OF SERVIG
REASON OUf E,.
HPCI A87-228 5/30/87 5/30/87 0/20.5 Steam leak on Turbine drain Turbine drein found during perfonnance of.
leakage reduction prograsa inspection E41 IIPCI, NOV's A87-236 6/5/87 6/6/87*
1/10.3 Valve would not stroke' full closed against-rated pressure and flow
- Duration for which IIPCI was required operable I
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2.0 Personnel and Man-rem'by Work and Job Function The following table entitled, "Shoreham Report of Personnel and Man-rem by Work and Job Function", was prepared to
. provide the information required by Technical Specification Sections 6.9.1.4 and 6.9.1.5.
The subtotals shown are calculated sums of the Radiation Work Permit (RWP) controlled work where the Totals and Grand Totals are measured by the TLDs.
For this reporting period, 1/1/87 through 12/31/87, no individual was exposed to more than 100 mrems/yr.
Therefore, a table indicating personnel exposures greater than 100 mrems/yr is not included in this report.
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- 4g LONG ISLAND LIGHTING COMPANY SHOREHAM NUCLEAR POWER STATION P.O. BOX G18, NORTH COUNTRY ROAD e WADING RIVER. N.Y.11792 JOHN O. LEON ARD, JR.
VKE PRESIDENT NUCLEAR OPEPATIONS FEB 26 BS9 SNRC-1431 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555 Annual Operating Report Shoreham Nuclear Power Station Unit 1 Docket No. 50-322 Gentlemen:
Attached is a copy of the Annual Operating Report.
It is submitted in compliance with the requirements of Shoreham Technical Specification Sections 6.9.1.4 and 6.9.1.5.
It also fulfills LILCO's commitment in Section II.K.3.17 of the Shoreham Updated Safety Analysis Report.
Should you have any questions, please do not hesitate to call my office.
Very truly yours,
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T.
D. Leonard, Jr/
Vice President (Nuclear Operations TD/1h Attachment cc:
R. Lo/S. Brown W. T.
Russell
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