ML20010J005

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Forwards LER 81-050/03L-0.Detailed Event Analysis Encl
ML20010J005
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 09/11/1981
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20010J006 List:
References
P-81226, NUDOCS 8109290493
Download: ML20010J005 (4)


Text

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[.4 El September 11, 1981 Fort St. Vrain Unit No. 1 P-91226

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Mr. Karl V. Seyfrit, Director

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  • Office of Inspection and Enforcement -

611 Ryan Plaza Drive Suite 1000 i Arlington, Texas 76012 i

Reference:

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

Dear Mr. Seyfrit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/81-050, 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. 50-267/81-050. , Very truly yours,

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J.( - } } % u w h ~ [ Don Warembourg Manager, fjuclear Production

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8109290493 810911 PDR ADOCK 05000267 s g PDR

g'RRENCE REPORT DISTRIBUTION Number of Copteg De pa r t me n t o f E ne r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter) San Francisco Operations office ! Attnt California Patet.t Group 1333 Broadway Oakland California 94612 . De p a r t me n t o f Ene rgy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (7 Letter) tr. Glen A. Newby. Chief JTR Branch Division of Nuclear Pawn Development itail Sration B-107 Washington, D.C. 20545 De pa r ttna nt o f Ene r gy - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter) Attn Project Manager 110 Yest A Street. Suite 460 y San Diego, California 92101 Mt. Karl V. Seyfrit, Director ------------------------- 1 (Original of P Letter Region IV and Copy of IER) Of fice of Inspection and Enforcement Nuclear Regulatsry Cotamission

  • 611 Ryan Plaza Drive Suite 1300 Arlington, Texas 76012 Di re c t o r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter. LER)

Of fice of Management Information and Progrs:a Control U. S. Nuclear Regulatory Cotanission Washington, D.C. 20555 5 Mr. Tichard Phelpe - - ~~ - - - - - - - - - - - - - - - - - - - - - - - - - - - 10 (Original of PPLC Letter I5V, CA. Site plus Two Copies. One Rep re sent ative Copy of P Letter. One General Atomic CoJDany Copy of LER)

  • P. O. Box 426 Platteville, Colorado 80651 M r . B i l l La va t e e - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 (P Letter, LER)

Nuclear Safety Ansivsis Center ' 3412 Hillview Avenue P. O. Box 10412 Palo Alto, California 94303

CC Resident Site Inspector ----------.-------.------- 1 (P Letter, LER)

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REPORT DATE: Seotember 11. 1981 REPORTABLE OCCURRENCE 81-050 Determined ISSUE O OCCURRENCE DATE: Aucust 14, 1981 Page 1 of,2 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELO COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651 REPORT NO. 50-267/81-050/03-L-0 Final l \ . IDENTIFICATION OF OCCURRENCE: On August 14, 1981, it was determined that the total dissolved solids in the plant nonradioactive liquid effluent exceeded 2300 parts per million on August 9, 1981. This is reportable per Fort St. Vrain Technical Specification AC 7.5.2(b)2 as a degraded mode cf LCO NR 1.1. EVENT DESCRIPTION: The reactor power level was increased from 45% starting August 3, 1981, and reached approximately 70% on August 6, 1981. The increase in power level was responsible for increased evaporation of the circulating water resulting in increased solids in the circulating water tower basin and higher tntal dissolved solids in the blowdown water. The increase was monitored by the Chemistry Department, but the increase on midnight shift on August 9, 1981, resulted in the limit of 2300 pa-ts per million being exceeded. The corrective action taken was to reduce cold side blowdown and increase raw water blowdown, which brought the total dissolved solids within limits by the next shift's sample. CAUSE DESCRIPTION: The increased total dissolved solids in the plant nonradioactive effluent was due to increased evaporation caused by reactor power level increases and improper blowdown adjustment. CORRECTIVE ACTION: The main .coling water blowdown was adjusted to reflect the plant power levels. No further corrective action is anticipated or required.

i e 4 REPORTABLE OCCURRENCE 81-050 i ISSUE O Page 2 of 2 i i i l-1 t 1 l Prepared By: Asa B. Reed 3[d ! Technical Services Technician t 1 i Reviewed By: WM WJ ^ 1 Mt1t McBride Technical Services Manager i

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i l Reviewed By: // , .: Edwin W H1 7 " l Station Manager i i Approved By: Y M Don Warembourg a 1 Manager, Nuclear Production 3 j i . i [ s

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