ML18139B846: Difference between revisions

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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND.., VIRGINIA 23261 R.H.LEASBUBG VxcE PREsXDENT NucLEAR OPERATIONS April 16, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND.., VIRGINIA 23261 R.H.LEASBUBG                                                           April 16,    1982 VxcE PREsXDENT NucLEAR OPERATIONS Mr. Harold R. Denton, Director                                                         Serial No. 229 Office of Nuclear Reactor Regulation                                                 NO/RMT:acm Attn: Mr. Steven A. Varga, Chief                                                       Docket Nos. 50-280 Operating Reactors Branch No. 1                                             50-281 Division of Licensing                                           License Nos. DPR-32 U. S. Nuclear Regulatory Commission                                                               DPR-37 Washington, D. C. 20555 Gentlemen:
Serial No. 229 NO/RMT:acm Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 This letter report is furnished in accordance with the provisions of Surry Power Station Technical Specification 4.14.C.1.
This letter report is furnished in accordance with the provisions of Surry Power Station Technical Specification 4.14.C.1.
During the period of 1000 hours to 1100 hours, April 3, 1982, the average rate of change of the Condenser Cooling Water Outlet Temperature was 4°F/hr. which exceeds the 3°F/hr. rate of change permitted by Technical Specification 4.14.A.3.
During the period of 1000 hours to 1100 hours, April 3, 1982, the average rate of change of the Condenser Cooling Water Outlet Temperature was 4°F/hr. which exceeds the 3°F/hr. rate of change permitted by Technical Specification 4.14.A.3.
At the time of this event, Unit 1 was at 100% power and Unit 2 was at 95% power. After removal of Unit 1 "C" water box from service for cleaning a seventh circulating water pump was started. In response to an increasing canal level the the water box outlets were throttled opened and the groin temperature dropped at a rate greater than 3°F/hr. The operator then stopped water box throttling to allow groin temperature to stabilize.
At the time of this event, Unit 1 was at 100% power and Unit 2 was at 95%
Personnel involved have been re-instructed on the importance of making gradual changes in flow through the water boxes. A search was conducted to determine if the temperature change had affected the river environment.
power.
No detrimental evidence was found. cc: Mr. James P. O'Reilly Regional Administrator Region II 0~.-8204190218 820416 -.: .. PDR ADOCK 05000 280 (.:*:*.$)*:;  
After removal of Unit 1 "C" water box from service for cleaning a seventh circulating water pump was started. In response to an increasing canal level the the water box outlets were throttled opened and the groin temperature dropped at a rate greater than 3°F/hr. The operator then stopped water box throttling to allow groin temperature to stabilize. Personnel involved have been re-instructed on the importance of making gradual changes in flow through the water boxes.
.. ; .. / ,.;,; .. ::, *. *. ,:.,,:/'*  
A search was conducted to determine if the temperature change had affected the river environment. No detrimental evidence was found.
.. .-.. ,,PP~ *:*Y: Very truly yours, . Q\_~\-l R. H. Leasburg}}
Very truly yours,
                                                                                                . Q\_~\-
l  R. H. Leasburg cc:           Mr. James P. O'Reilly Regional Administrator Region II 0 ~.-8204190218                           820416 -
.: .. PDR ADOCK 05000 280
(.:*:*.$)*:; .. ;.. / ,.;,; .. ::, *. *. ,:.,,:/'*.. .-.. ,,PP~ *:*Y:}}

Latest revision as of 03:03, 21 October 2019

Ro:On 820403,average Rate of Change of Condenser Cooling Water Outlet Temp Exceeded Permitted Rate.Caused by Operator Error.Personnel Reinstructed
ML18139B846
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/16/1982
From: Leasburg R
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
References
229, NUDOCS 8204190218
Download: ML18139B846 (1)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND.., VIRGINIA 23261 R.H.LEASBUBG April 16, 1982 VxcE PREsXDENT NucLEAR OPERATIONS Mr. Harold R. Denton, Director Serial No. 229 Office of Nuclear Reactor Regulation NO/RMT:acm Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen:

This letter report is furnished in accordance with the provisions of Surry Power Station Technical Specification 4.14.C.1.

During the period of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> to 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, April 3, 1982, the average rate of change of the Condenser Cooling Water Outlet Temperature was 4°F/hr. which exceeds the 3°F/hr. rate of change permitted by Technical Specification 4.14.A.3.

At the time of this event, Unit 1 was at 100% power and Unit 2 was at 95%

power.

After removal of Unit 1 "C" water box from service for cleaning a seventh circulating water pump was started. In response to an increasing canal level the the water box outlets were throttled opened and the groin temperature dropped at a rate greater than 3°F/hr. The operator then stopped water box throttling to allow groin temperature to stabilize. Personnel involved have been re-instructed on the importance of making gradual changes in flow through the water boxes.

A search was conducted to determine if the temperature change had affected the river environment. No detrimental evidence was found.

Very truly yours,

. Q\_~\-

l R. H. Leasburg cc: Mr. James P. O'Reilly Regional Administrator Region II 0 ~.-8204190218 820416 -

.: .. PDR ADOCK 05000 280

(.:*:*.$)*:; .. ;.. / ,.;,; .. ::, *. *. ,:.,,:/'*.. .-.. ,,PP~ *:*Y:

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