ML19225A854: Difference between revisions

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| number = ML19225A854
| number = ML19225A854
| issue date = 05/20/1979
| issue date = 05/20/1979
| title = Responds to NRC 790426 Ltr Re Violation Noted in IE Insp Rept 50-293/79-04.Corrective Actions:Necessary Steps Taken to Conform W/Tech Spec Requirement of 50% Reactor Power Limitation
| title = Responds to NRC Re Violation Noted in IE Insp Rept 50-293/79-04.Corrective Actions:Necessary Steps Taken to Conform W/Tech Spec Requirement of 50% Reactor Power Limitation
| author name = Andognini G
| author name = Andognini G
| author affiliation = BOSTON EDISON CO.
| author affiliation = BOSTON EDISON CO.
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = NUDOCS 7907200444
| document report number = NUDOCS 7907200444
| title reference date = 04-26-1979
| package number = ML19225A852
| package number = ML19225A852
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
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=Text=
=Text=
{{#Wiki_filter:.#f*. . .'BOSTON EDISON COMPANY GENERAL omCES 800 BoyLRTON STREET B O S TQ N.
{{#Wiki_filter:.#
M A S S A C H U S ETTS o2199
f*
: c. CARL ANOCGNiN1 MANAGER NUCLEAR QPER ATIONS DEPARTMENT May 20, 1979 BECo. Ltr. #79- 95 Mr. Eldon J. Brunner, Chief Reactor Operations and Nuclear Support Branch Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA.
BOSTON EDISON COMPANY GENERAL omCES 800 BoyLRTON STREET B O S TQ N. M A S S A C H U S ETTS o2199
: c. CARL ANOCGNiN1 MANAGER NUCLEAR QPER ATIONS DEPARTMENT May 20, 1979 BECo. Ltr. #79-95 Mr. Eldon J. Brunner, Chief Reactor Operations and Nuclear Support Branch Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA.
19406 License No. DPR-35 Docket No. 50-293 Response to IE Inspection No. 79-04
19406 License No. DPR-35 Docket No. 50-293 Response to IE Inspection No. 79-04


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Boston Edison Company's response to that item is presented as follows:
Boston Edison Company's response to that item is presented as follows:
Deficiency Technical Specification (TS) 4.7.D.1.b(2) requires that reactor power be less than 50" when tripping the main steam isolation valves individually, and verifying closure ti e.
Deficiency Technical Specification (TS) 4.7.D.1.b(2) requires that reactor power be less than 50" when tripping the main steam isolation valves individually, and verifying closure ti e.
Contrary to the above, Procedure Number 8.7.4.4, Main Steam Isolation Valve Trip, written to satisfy the above TS requirement contained acceptance criteria allowing the surveillance test to be perfor=ed at a reactor power less than 60%, a less conservative value.
Contrary to the above, Procedure Number 8.7.4.4, Main Steam Isolation Valve Trip, written to satisfy the above TS requirement contained acceptance criteria allowing the surveillance test to be perfor=ed at a reactor power less than 60%,
Further, surveillance tests performed May 28, 1978 and February 18, 1978 were conducted at reactor power levels of 55% and 52.5%, respectively.
a less conservative value.
Further, surveillance tests performed May 28, 1978 and February 18, 1978 were conducted at reactor power levels of 55% and 52.5%,
respectively.
Respoase Procedure Number 8.7.4.4 has been changed and is now in conformance with the 50%
Respoase Procedure Number 8.7.4.4 has been changed and is now in conformance with the 50%
reactor power limitation as stated in the Technical Specifications.
reactor power limitation as stated in the Technical Specifications.
A Technical Specification change to remove the power restriction requirement is currently in draft form and will be submitted in a subsequent letter.
A Technical Specification change to remove the power restriction requirement is currently in draft form and will be submitted in a subsequent letter.
790720cd-- -366 030  
790720cd 366 030
.+..BOSTON 'EoisoN COMPANY
 
-Mr. Eldon J. Brunner, Chief May 20, 1979 Page 2 At the present time we are in compliance in this area.
+
BOSTON 'EoisoN COMPANY Mr. Eldon J. Brunner, Chief May 20, 1979 Page 2 At the present time we are in compliance in this area.
We 'oelieve that this letter is responsive to your concerns.
We 'oelieve that this letter is responsive to your concerns.
However, should you have any further questions or concerns please contact us.
However, should you have any further questions or concerns please contact us.
Very truly yours, j n!O " 366 031}}
Very truly yours, j
n!O "
366 031}}

Latest revision as of 15:37, 4 January 2025

Responds to NRC Re Violation Noted in IE Insp Rept 50-293/79-04.Corrective Actions:Necessary Steps Taken to Conform W/Tech Spec Requirement of 50% Reactor Power Limitation
ML19225A854
Person / Time
Site: Pilgrim
Issue date: 05/20/1979
From: Andognini G
BOSTON EDISON CO.
To: Brunner E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19225A852 List:
References
NUDOCS 7907200444
Download: ML19225A854 (2)
v • d • e


Text

.#

f*

BOSTON EDISON COMPANY GENERAL omCES 800 BoyLRTON STREET B O S TQ N. M A S S A C H U S ETTS o2199

c. CARL ANOCGNiN1 MANAGER NUCLEAR QPER ATIONS DEPARTMENT May 20, 1979 BECo. Ltr. #79-95 Mr. Eldon J. Brunner, Chief Reactor Operations and Nuclear Support Branch Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA.

19406 License No. DPR-35 Docket No. 50-293 Response to IE Inspection No. 79-04

Dear Sir:

Inspection No. 79-04, dated April 26, 1979, contained one item of non-compliance.

Boston Edison Company's response to that item is presented as follows:

Deficiency Technical Specification (TS) 4.7.D.1.b(2) requires that reactor power be less than 50" when tripping the main steam isolation valves individually, and verifying closure ti e.

Contrary to the above, Procedure Number 8.7.4.4, Main Steam Isolation Valve Trip, written to satisfy the above TS requirement contained acceptance criteria allowing the surveillance test to be perfor=ed at a reactor power less than 60%,

a less conservative value.

Further, surveillance tests performed May 28, 1978 and February 18, 1978 were conducted at reactor power levels of 55% and 52.5%,

respectively.

Respoase Procedure Number 8.7.4.4 has been changed and is now in conformance with the 50%

reactor power limitation as stated in the Technical Specifications.

A Technical Specification change to remove the power restriction requirement is currently in draft form and will be submitted in a subsequent letter.

790720cd 366 030

+

BOSTON 'EoisoN COMPANY Mr. Eldon J. Brunner, Chief May 20, 1979 Page 2 At the present time we are in compliance in this area.

We 'oelieve that this letter is responsive to your concerns.

However, should you have any further questions or concerns please contact us.

Very truly yours, j

n!O "

366 031

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