05000267/LER-1982-029, Forwards LER 82-029/03X-1.Detailed Event Analysis Encl

From kanterella
Jump to navigation Jump to search
Forwards LER 82-029/03X-1.Detailed Event Analysis Encl
ML20062P103
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 08/17/1982
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20062P106 List:
References
P-82325, NUDOCS 8208240074
Download: ML20062P103 (5)
v • d • e


LER-1982-029, Forwards LER 82-029/03X-1.Detailed Event Analysis Encl
Event date:
Report date:
2671982029R00 - NRC Website
v • d • e

text

_.

public Service Company F Odendo 4

8 16305 Road 19 1/2, Platteville, Colorado 80651-9298 August 17, 1982 Fort St. Vrain kh kl 3

I uum l

\\

Mr. John T. Collins, Regional Administrator i

Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011

Reference:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Collins:

l Enclosed please find a copy of Reportable Occurrence Report No. 50-267/82-029, Revised Final, submitted per the requirements of Technical Specification AC 7.5.2(b)2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/82-029.

(

Very truly yours, I

gm%/g Don Warembourg F

Manager, Nuclear Production DW/cls Enclosure

~

l-cc: Director, MIPC p

/ (<

820 8 z4 0014 b a

u-w FIPORTABLE OCCURRENCE MSTRIBUTION Number of Cor tes De p a r t :e n t o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Le t te r)

San Francisco Operations Of fice Attn : Califomia Patent Group 1333 Broadeay Oakland, Califo rnia 94612 De p a r tre n t o f En e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter)

Mr. Glen A. Newby, Chie f H!R Branch Division of Nuclear Power Development Mail S tation 3-107 Washin gton, D.C.

20545 De p artmen t o f E n e r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Atta: Project Manager 110 West A S t ree t, Suite 460 San Diego, California 92101 Mr. John T. Collins, Regional Adminis trator ------------------

(Original of P latter)

Region IV Nuclear Regulatory Co-missicn 611 Ryan Plaza Drive Suite 1000 Arlin gt on, Te xas 76011 Mr. George Kuzmycz - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Nuclear Regulatory Coc=ission 7920 Norf olk Avenue Be thesda, Maryland 20034 D i re c t o r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P latter)

Of fice of Management Informatica and Progra:2 Control Nuclear Regulatorv Cocnission Washington, D.C.

20555 Re c o r ds Ce n t e r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1 (P Letter)

Ins titute cf Nuclear Pa.er Operations 1820 Water Place Atlanta, Georgia 30339 Mr. Richa rd Phe lp s FS V, GA, Site Rep re sen t ative - - - - - - - - - - - - - - -

  • 1 (P Letter)

General Atanic Company 16564 Weld County Road 19 1/2 P lat te ville, Colorado 80651 NRC Resident Site inspector --------------------------

1 (P Le t te r) 5

1 REPORT DATE:

August 17, 1982 REPORTABLE CCCURRENCE 82-029 153UE 1 OCCURRENCE DATE:

July 12, 1982 Page 1 of 3 FORT ST. VRAIN NUCLEAR GENERATING STATICN PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298 REPORT NO. 50-267/82-029/03-X-1 Revised Final IDENTIFICATION OF CCCURRENCE:

On three occasions in July, 1982, emergency feedwater was unavailable to drive the helium circulator pelton wheels.

With the reactor operating at approximately 7C% power during each occasion, this constitutes a degraced mode of Fort St. Vrain Technical Specification LCO 4.2.2(a) and is reportable per AC 7.5.2(b)2.

EVENT

DESCRIPTION

Event #1 At 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on July 12, 1982, Loop 2 emergency feedwater neader to Loop 2 nelium circulator pelton wheel crives was isolated to perform maintenance on leaking safety valves, V-21523 and V-21543. However, efforts to cool the header down to safe working conditions were not successful due to unexpected steam in-leakage.

Maintenance efforts were curtailed, and the header was returned to service at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> l

on July 12, 1982.

l Event #2 At 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on July 20, 1982, both Loop 1 and Loop 2 emergency feedwater headers to the helium circulator pelton wheel drives were isolated

  • o perform maintenance on the leaking Loop 1 safety valves, V-21522 and V-21542, and Loop 2 safety valves, V-21523 and V-21543.

At 2211 nours on July 20, 1982, botn loops were returned to service for testing and werc consicered operable.

Event #3 At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on July 21, 1952, Loop 1 and Loop 2 emergency feedwater heacers to tne helium circulator pelton aneel drives were again cleared out to cerform maintenance on safety valves, V-21522, l V-21523, V-21542, and V-21543.

At 0650 hours0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br /> on July 22, 1932, both Loop 1 and Loop 2 emergency feedaater headers were returned to service.

i i

i

_ REPORTABLE OCCURRENCE 82-029 ISSUE 1 Page 2 of 3 On all three occasions the emergency feedwater headers to the helium circulator pelton wheel drives were returned to service within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time limit allowed by Fort St. Vrain Technical Specification LCO 4.2.2(a).

During each occasion, the emergency condensate and firewater headers to the pelton wheel drives remained operable and would have provided the motive force necessary for driving the helium circulators had the need arisen.

p

CAUSE

DESCRIPTION:

l On each occasion, the emergency feedwater headers were taken out of service in order to perform maintenance on leaking pelton water drive header safety valves.

The safety valve leakage is attributed to 1

normal wear.

CORRECTIVE ACTION:

Event #1 4

l The loop 2 emergency feedwater header was returned to service after nine hours. No maintenance was performed.

^

Event #2 i

Both Loop 1 and Loop 2 emergency feedwater headers were returned to service after 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. Maintenance was performed on the pelton wheel drive header safety valves.

l Event #3 Both Loop 1 and Loop 2 emergency feedwater headers were returned to l service after 23.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Maintenance was completed on the pelton wheel drive header safety valves.

l I

I i

)

i

t REPORTABLE CCCURRENCE 82-029 ISSUE 1 Page 3 of 3 Prepared By:

(

'k Paul A." Tramp

/

Technical Services Technician Reviewed By:

t/$(~ [ '

Cnarles Fulier Technical Services Enejnee ng Sucervisor

/

w Reviewed By:

/

Edwin C-: Ni l'1 /

Station Manager Apcroved By:

1 #Medk, Ocn Warerecurg

/

Manager, Nuclear Production

Retrieved from "https://kanterella.com/w/index.php?title=05000267/LER-1982-029,_Forwards_LER_82-029/03X-1.Detailed_Event_Analysis_Encl&oldid=4450812"