ML18139B231: Difference between revisions

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| issue date = 04/01/1981
| issue date = 04/01/1981
| title = Ro:On 810322,condenser Cooling Water Outlet Temp Exceeded Tech Spec Limit.Caused by Lack of Svc Water Flow. Investigation Is in Progress
| title = Ro:On 810322,condenser Cooling Water Outlet Temp Exceeded Tech Spec Limit.Caused by Lack of Svc Water Flow. Investigation Is in Progress
| author name = SYLVIA B R
| author name = Sylvia B
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name = DENTON H R, VARGA S A
| addressee name = Denton H, Varga S
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000281
| docket = 05000281
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=Text=
=Text=
{{#Wiki_filter:.. s e VIRGINrA ELECTRIC AND PowER Coll-.l:eANY RXCHMOND,VJ:RGXN:tA.
{{#Wiki_filter:.                       e VIRGINrA ELECTRIC AND PowER Coll-.l:eANY RXCHMOND,VJ:RGXN:tA. 23261 April 1, 1981 Mr. Harold R. Denton, Director                             Serial No. 229 Office of Nuclear Reactor Regulation                       NO/RMT:ms Attn: Mr. Steven A. Varga, Chief                           Docket No. 50~281 Operating Reactors Branch No. 1                     License No. DPR-37 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
23261 April 1, 1981 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:
This letter report is submitted in accordance with the provisions of Surry Power Station Technical Specification 4.14.C.l.
Serial No. 229 NO/RMT:ms Docket No. 50~281 License No. DPR-37 This letter report is submitted in accordance with the provisions of Surry Power Station Technical Specification 4.14.C.l.
During the period from 1800 to 1900 on March 22, 1981, the condenser's cooling water outlet temperature exceeded the maximum average rate of change of 3°F/hr permitted by Technical Specification 4. 14. A. 3. The average rate of change during this period was 4°F/hr. At the time of this event, Unit No. 1 was at cold shutdown and Unit No. 2 was at 43% power escalating to full power operation.
During the period from 1800 to 1900 on March 22, 1981, the condenser's cooling water outlet temperature exceeded the maximum average rate of change of 3°F/hr permitted by Technical Specification  
: 4. 14. A. 3. The average rate of change during this period was 4°F/hr. At the time of this event, Unit No. 1 was at cold shutdown and Unit No. 2 was at 43% power escalating to full power operation.
The lack of service water flow through Unit No. 1 is believed to be a major contributing factor to this event. It should be recognized that all due care and caution were exercised during the power escalation.
The lack of service water flow through Unit No. 1 is believed to be a major contributing factor to this event. It should be recognized that all due care and caution were exercised during the power escalation.
A search was conducted to determine if the temperature change had affected the river environment.
A search was conducted to determine if the temperature change had affected the river environment. No detrimental evidence was found.
No detrimental evidence was found. cc: Mr. James P. O'Reilly Very truly yours, 1~ B. R. Sylvia Manager -Nuclear Operations and Maintenance}}
Very truly yours, 1~
B. R. Sylvia Manager - Nuclear Operations and Maintenance cc:  Mr. James P. O'Reilly s}}

Latest revision as of 03:15, 21 October 2019

Ro:On 810322,condenser Cooling Water Outlet Temp Exceeded Tech Spec Limit.Caused by Lack of Svc Water Flow. Investigation Is in Progress
ML18139B231
Person / Time
Site: Surry Dominion icon.png
Issue date: 04/01/1981
From: Sylvia B
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
References
229, NUDOCS 8104060751
Download: ML18139B231 (1)
v • d • e


Text

. e VIRGINrA ELECTRIC AND PowER Coll-.l:eANY RXCHMOND,VJ:RGXN:tA. 23261 April 1, 1981 Mr. Harold R. Denton, Director Serial No. 229 Office of Nuclear Reactor Regulation NO/RMT:ms Attn: Mr. Steven A. Varga, Chief Docket No. 50~281 Operating Reactors Branch No. 1 License No. DPR-37 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

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

During the period from 1800 to 1900 on March 22, 1981, the condenser's cooling water outlet temperature exceeded the maximum average rate of change of 3°F/hr permitted by Technical Specification 4. 14. A. 3. The average rate of change during this period was 4°F/hr. At the time of this event, Unit No. 1 was at cold shutdown and Unit No. 2 was at 43% power escalating to full power operation.

The lack of service water flow through Unit No. 1 is believed to be a major contributing factor to this event. It should be recognized that all due care and caution were exercised during the power escalation.

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

Very truly yours, 1~

B. R. Sylvia Manager - Nuclear Operations and Maintenance cc: Mr. James P. O'Reilly s

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