ML20071B057

Forwards Addl Commitment to SER Open Item 64 Re Loose Parts Monitoring Sys.Feedwater Flow Will Be at Least 50% of Rated Flow When Calibr of Loose Parts Monitoring Sys Sensors Completed

ML20071B057
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	02/14/1983
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SNRC-839, NUDOCS 8302250312
Download: ML20071B057 (6)

Text

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) 8 LONG ISLAND LIGHTING COMPANY e Afi t'Ol l' g Mwmpfg SHOREHAM NUCLEAR POWER STATION

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• WADING RIVER, N.Y.11792 Direct Dial Number February 14, 1983 SNRC-839 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Loose Parts Monitoring System Safety Evaluation Report Item #64

Reference:

(1) Letter SNRC-769 dated September 14, 1982 (2) Region I Insepction Report 50-322/82-02

Dear Mr. Denton:

In the reference 1 letter, LILCO forwarded additional information on Shoreham's Loose Parts Monitoring System (LPMS) consisting of the following:

(1) LPMS Description and cost / benefit analysis for separation.

(2) Proposed test program to determine the utilization of the Deliberate Plant Maneuver Detector.

(3) Various plant procedures including a draft of STP

! 814, Startup Test Procedure.

l This informatien has been received by the staff and, based on recent l discussions, it has been determined that one additional commitment must be formally made by LILCO prior to resolution of this item with NRR. To this end, and in response to the Ref. 2 inspection item, when calibration (system sensitivity adjustment and alarm logic adjustment) of the feedwater LPMS sensors is done, feedwater flow l

will be at least 50% rated flow.

l Copies of the pertinent pages of the revised draft startup test

procedure (STP 814, refer to sections 8.4.2 and 8.5.2) are enclosed l denoting this commitment.

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_; February l',~1983 4 '

Mr. Harold R..Denton Page-2 Based..on the.above.noted discussions,.it is LILCO's understanding ~

.that this commitma.E is sufficient to close this issue with NRR (SER item number 64) . LILCO-will continue to work-with Region I-and NRR regarding utilization of the deliberate plant maneuver.

. inhibit feature of the LPMS (Inspection item No. 322/82-02-05).

Should you.have any question, please contact this office.

Verty truly yours,.

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- J. L. Smith Manager,-Special Projects.. ,_

. Shoreham Nuclear Power Station '

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- JLS:bc cc: J.-Higgins '

. Parties' Listed in Attachment 1 s

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ATTACHMENT 1 Lawrence Brenner, Esq. Herbert H. Brown, Esq.

Administrative Judge Lawrence Coe Lanpher, Esq.

Atomic Safety and Licensing Karla J. Letsche, Esq.

Board Panel Kirkpatrick, Lockhart, Hill.

U.S. Nuclear Regulatory Commission Christopher & Phillips Washington, D.C. 20555 8th Floor 1900 M Street, N.W.

Washington, D.C. 20036 Dr. Peter A. Morris Administrative Judge Atomic Safety and Licensing Mr. Marc.W. Goldsmitia Board Panel Energy Research Group U.S. Nuclear Regulatory Commission 4001 Totten Pond Road Washington, D.C. 20555 Waltham, Massachusetts 02154 Dr. James H. Carpenter MHB Technical Associates Administrative Judge 1723 Hamilton Avenue Atomic Safety and Licensing Suite K Board Panel San Jose, California 95125 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Stephen B. Latham, Esq.

Twomey, Latham & Shea

Daniel F. Brown, Esq. 33 West Second Street

Attorney P.O. Box 398 l Atomic Safety and Licensing Riverhead, New York 11901 Board Panel U.S. Nuclear ~ Regulatory Commission Washington, D.C. 20555 Ralph Shapiro, Esq.

! Cammer and Shapiro, P.C.

9 East 40th Street

Bernard M. Bordenick, Esq. New York, New York 10016 David A. Repka, Esq.

! U.S. Nuclear Regulatory Commission l Washington, D.C. 20555 ,

Matthew J. Kelly, Esq.

State of New York Department of Public Service L Three Empire State Plaza Alban:r, New York 12223 l

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Submitted:

Approved:

(Plant Manager)

STP Number 814 Revision Date Eff, s-.

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3 Loose Parts Monitoring.

1.0 PURPOSE 1.l' Establish base line data for later reference-in the detection of loose parts.

1.2 Establish Loose Parts Monitoring System alert adjust-ments for normal plant operating conditions and verify simulated impacts are detected.

1.3 Demonstrate that the Loose Parts Monitoring System sensitivity meets the RG 1.133 requirements'of detecting _0.5 ft-lb impacts 3 feet from the sensor.

1.4 Determine the plant maneuvers'that generate spurious loose parts monitoring system alarms.

2.0 DESCRIPTION

2.1 The Loose Parts Monitoring System response will be monitored and recorded.

2.2- The information collected will-be evaluated to determine LPM alert settings and to ensure adequate instrument sensitivity and response.

2.3 Monitor LPMS response during deliberate plant maneuvers and establish which plant maneuvers should disable the LPMS so spurious alarms will not be generated during deliberate plant maneuvers.

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' 8. 4' System Sensitivity Adjustment This test measures the background

• noise levels under

. normal plant' conditions and calculates the required

'alertfthreshold~settingLto meetithe Regulatory Guide

,1.133 sensitivity requirements.

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' -- 8.4.1 Verify? that procedureisteps 8.1 and 8.2 have been completed.

Verified Date

, 8. 4. 2 - ' Verify ithat the plant con'ditions -are within -

'the range of conditions listed below. Record the. actual plant conditions.in Table 3.

Power  : 50 - 100%

Feedwater Flowi- 50 - 100%

Recirc.-Flow : 50 - 100%

Verified Date 8.4.3 Contact control room personnel and verify that the-plant should remain stable for the

-remainder of Section 8.4 of the procedure.

Verified Date 8.4.4 Set all switches and controls in accordance with Attachment 4.

Verified Date 8 .~ 4 . 5 Depress the system reset switch and verify that all TEC-1432 status LEDs are green.

Verified Date 8.4.6 Record the gain and filter settings of the TEC-932 amplifiers in Table 3.

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8.5 - System Alarm Logic Adjustment

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Thi'sitest adjusts the alarm logic.of.the TEC model 1433C control module to prevent false alarms while maintaining the sensitivities required by:RG 1.133.- This. adjustment is-performed by monitoring the~ rate _at whichLthe TEC model 1432 impact detectors generate spurious alert' signals ,

and. determining the appropriate alert rate '

setting for. preventing false' alarms.

8. 5.1 - Verify'that procedure steps 8.1, 8.2 and 8.4 have'been performed <

Verified Date.

8.5.2 Verify.that plant conditions are within the range of. conditions listed below and will remain so for the duration of procedure Section 8.5. Record the actual reactor conditions in Table 4.

Power  : 50 - 100%

Feedwater Flow: 50 - 100%

Recirc~. Flow  : SO - 100%

Verified Date 8.5.3' Power down-the LPMS and connect the 6 channel strip chart recorder to the LPM system in order _to monitor the (later) alert signals of all of the_TEC 1432 impact detectors. 'When completed, power the LPM system back up.

1 Verified Date 8.5.4 Set all switches and controls in accordance with Attachment 4.

Verified Date 0.5.5 Power up the strip chart recorder and set the paper speed so that an hours worth of data collection will not produce an unwiedly amount of paper.

Verified Date 18 j