ML18139B287: Difference between revisions

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| issue date = 05/01/1981
| issue date = 05/01/1981
| title = Ro:On 810418,condenser Cooling Water Outlet Temp Exceeded Max Average Rate of Change of 3F/hr Per Tech Spec 4.14.A.3. Lack of Svc Water Flow Believed to Be Contributing Factor. Tube Leaks Repaired.River Environ Not Affected
| title = Ro:On 810418,condenser Cooling Water Outlet Temp Exceeded Max Average Rate of Change of 3F/hr Per Tech Spec 4.14.A.3. Lack of Svc Water Flow Believed to Be Contributing Factor. Tube Leaks Repaired.River Environ Not Affected
| 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:' ' ., e VIRGINIA ELECTRIC A.ND POWER COMPANY R:u;:HMOND,VIRGINIA 23261 May 1, 1981 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Operating Reactor Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555  
{{#Wiki_filter:'
e VIRGINIA ELECTRIC A.ND POWER COMPANY R:u;:HMOND,VIRGINIA 23261 May 1, 1981 Mr. Harold R. Denton, Director                     Serial No. 277 Office of Nuclear Reactor Regulation               NO/RMT:jmj Attn: Mr. Steven A. Varga, Chief                   Docket No. 50-281 Operating Reactor Branch No. 1             License No. DPR-37 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555


==Dear Mr. Denton:==
==Dear Mr. Denton:==
Serial No. 277 NO/RMT:jmj 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 0430 to 0530 on April 18, 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.
This letter report is submitted in accordance with the provisions of Surry Power Station Technical Specification 4.14.C.l.
The average rate of change during this period was 4°F/hr. At the time of this event, Unit No. 1 was at cold down and Unit No. 2 was in the process of shutting down, at 10% power. The lack of service water flow through Unit No. 1 is believed to be a contributing factor to this event. Feedwater heater tube leaks were creating heater level control problems, especially at low power levels. This necessitated the use of a higher than normal ramprate, thereby providing increased turbine protection.
During the period from 0430 to 0530 on April 18, 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 shut-down and Unit No. 2 was in the process of shutting down, at 10% power.
The tube leaks have subsequently been repaired.
The lack of service water flow through Unit No. 1 is believed to be a contributing factor to this event. Feedwater heater tube leaks were creating heater level control problems, especially at low power levels. This necessitated the use of a higher than normal ramprate, thereby providing increased turbine protection. The tube leaks have subsequently been repaired.
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 detrilllental evidence was found.
No detrilllental evidence was found. cc: Mr. James P. O'Reilly Very truly yours, 0.f~ B. R. Sylvia Manager -Nuclear Operations and Maintenance}}
Very truly yours,
                                                    ~  0.f~
B. R. Sylvia Manager - Nuclear Operations and Maintenance cc:  Mr. James P. O'Reilly}}

Latest revision as of 01:10, 3 February 2020

Ro:On 810418,condenser Cooling Water Outlet Temp Exceeded Max Average Rate of Change of 3F/hr Per Tech Spec 4.14.A.3. Lack of Svc Water Flow Believed to Be Contributing Factor. Tube Leaks Repaired.River Environ Not Affected
ML18139B287
Person / Time
Site: Surry Dominion icon.png
Issue date: 05/01/1981
From: Sylvia B
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Varga S
Office of Nuclear Reactor Regulation
References
NUDOCS 8105050252
Download: ML18139B287 (1)
v • d • e


Text

'

e VIRGINIA ELECTRIC A.ND POWER COMPANY R:u;:HMOND,VIRGINIA 23261 May 1, 1981 Mr. Harold R. Denton, Director Serial No. 277 Office of Nuclear Reactor Regulation NO/RMT:jmj Attn: Mr. Steven A. Varga, Chief Docket No. 50-281 Operating Reactor Branch No. 1 License No. DPR-37 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

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

During the period from 0430 to 0530 on April 18, 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 shut-down and Unit No. 2 was in the process of shutting down, at 10% power.

The lack of service water flow through Unit No. 1 is believed to be a contributing factor to this event. Feedwater heater tube leaks were creating heater level control problems, especially at low power levels. This necessitated the use of a higher than normal ramprate, thereby providing increased turbine protection. The tube leaks have subsequently been repaired.

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

Very truly yours,

~ 0.f~

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

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