05000245/LER-1982-029, Forwards LER 82-029/03L-0.Detailed Event Analysis Encl

Forwards LER 82-029/03L-0.Detailed Event Analysis Encl

ML20028C717
Person / Time
Site:	Millstone
Issue date:	01/07/1983
From:	Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20028C718	List: 05000245/LER-1982-029, Forwards LER 82-029/03L-0.Detailed Event Analysis Encl 05000245/LER-1982-029-03, /03L-0:on 821207,fire Water Storage Tank a & B Levels Found Below Tech Specs.Caused by Stripped Gear in Tank a & Sticking Gear in Tank B.Tanks Refilled.Gear & Valve Lubricated
References
MP-4563, NUDOCS 8301140034
Download: ML20028C717 (3)

LER-1982-029, Forwards LER 82-029/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2451982029R00 - NRC Website

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t January 7, 1983 MP-4563 Mr. Ronald C. Haynes Regional Administrator, Region 1 U. S. Nuclear Regulatory Cmmission Regional Office 631 Park Avenue King of Prussia, PA.

19406

Reference:

Provisional License DPR-21 Docket No. 50-245 Reportable Occurrence RO 82-29/3L

Dear Mr. Haynes:

This letter forwards the Licensee Event Report for Reportable Occurrence RO 82-29/3L. The PIR was originally classified as a 30 day reportable ard the Licensee Event Report written in accordance with Technical Specification 6.9.1.9.b.

Higher management review and re-evaluation, however, has determined the PIR was classified incorrectly and the Licensee Event Peport should have been sutmitted in accordance with Technical Specification 6.9.2.f.

Because the reporting requirments of Technical Specification 6.9.2.f can not be met, Millstone Unit I now submits this Licensee Event Report. Three additional copies of the report are enclosed.

Yours truly, NORIBEAST hTCLEAR ENERGY COMPANY N

E. J. Mroczka Station Superintendent Millstone Nuclear Power Station EJM/TST:mo

Attachment:

LER RO 82-29/3L cc: Director, Offi of Inspection and Enforcement, Washington, D. C.

(30)

Director, Office of Managment Information and Program Control, Washington, D. C.

(3)

U. S. Nuclear Regulatory Cmmission, c/o Document Managment Branch, Washington, D. C. 20555 8301140034 830107 DRADOCK05000g th

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ATDC15ENT 'IO LER 82-29/3L NORMEAST NUCLEAR BGNY CWPANY MTTJRIGIE NUCLEAR POWER STATICN - UNIT 1 PROVISICNAL LICENSE NWBER DPR-21 DOCKET NUMBER 50-245

- IDENTIFICATIN & OOCURRENCE Conditions l=Hng to operation in a demba node permitted by a limiting condition for operation occurred when fire water storage tank levels A and B were found to be below the mininum required volumes of Technical Specification.

CCNDITICNS PRIOR 'IO OOCURRENCE Prior to occurrence the unit was operating at a steady state power level of 100 ~

percent.

DESCRIPTIN T OOCURRENCE Ch Decua;er 7,1982, at 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br />, while performing routine rounds, fire water storage tank A and B levels were found to be at 190, 153 gallons and 190,074.

gallons respectively. 'Ihe fire water storage tanks were inmediately filled to above the required Technical Specification limit. Technical Specification 3.12.A.l.a requires two fire suppression water supplies, each with a mininum contained volume of 200,000 gallons.

APPARENT CAUSE T OCCURRENCE Investigation revealed the A and B fire water make-up valve operators to be inoperative. Disassembly of

'A' make-up valve operator showed a stripped gear caused by manual operation of the valve without declutching the motor.

'B' notar operator was found to have a sticking brake. Additionally

'B' make-up valve was binding.

ANALYSIS T OOCURRENCE Operability of the fire suppression system ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in any portion.

of the facility where safety related equipment is located. 'Ihe collective ca-pability of the fire suppression systen is adequate to minimize potential damage g

to safety related equipnent.

Assuming the worst single fire event, Millstone II main transformer, a 3900 gallon-per minute (ggn) water supply would be the maximum output with both fire water punps running. This provides ample water to extinguish the fire within 20 to 30 minutes. Given a volume of 380,227 gallons (190,074 + 190,153) taking suction at 3900 gpn, a 97.5 minute supply of water would be available. When operating with the Technical Specification requirement of 200,000 gallons, a 102.56 minute supply i

of water would be available, a 5 minute difference. An additional 5 minute supply at that point would nest likely have no significant inpact on the extinguishment of the fire.

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OCRRECTIVE ACTIN

. The gear in 'A' make-up valve operator was rotated away frcan the stripped teeth and lubricated. 'Ihe sticking brake in 'B' make-up valve operator was. removed and the valve lubricated.-

The preventive maintenance frequency'on both valves was increased in order to reduce the nunber of failures. Additionally, an engineering work request was generated to look into the feasibility of changing the operators.

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