ML20112F823: Difference between revisions
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{{#Wiki_filter:,_. _ _ _ - -. | {{#Wiki_filter:,_. _ _ _ - -. | ||
SOSTON EDISON COMPANY 800 BovLaTON STREET BOSTON. MASSACHUSETTS 02199 wtLLIAM O. HARRINGTON | SOSTON EDISON COMPANY 800 BovLaTON STREET BOSTON. MASSACHUSETTS 02199 wtLLIAM O. HARRINGTON January 8, 1985 BEco Ltr. #85-002 | ||
""* = | |||
Director. 0ffice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission | |||
BEco Ltr. #85-002 Director. 0ffice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission | . Washington, D.C. | ||
20555 ATTN: Document Control Desk Docket Nuncer 50-293 License DPR-35 | |||
==Subject:== | ==Subject:== | ||
| Line 28: | Line 28: | ||
==Dear Sir:== | ==Dear Sir:== | ||
A Secondary Containment Leak Rate Test (8.7.3) was satisfactorily performed on October 28, 1984 and is hereby reported as required by PNPS Technical | A Secondary Containment Leak Rate Test (8.7.3) was satisfactorily performed on October 28, 1984 and is hereby reported as required by PNPS Technical | ||
-Specification 6.9.C.3. | |||
This test was performed to verify secondary containment integrity at Refueling Outage #6 prior to refuel. | |||
This secondary containment leak rate test demonstrated that the Standby Gas | This secondary containment leak rate test demonstrated that the Standby Gas | ||
' Treatment System (SGTS) was capable of maintaining greater than 1/4 inch of water vacuum in the secondary containment, as required by PNPS Technical Specification 4.7.C.1.c. | |||
The test was initiated through the_use of permanently installed test switches which simultaneously isolated the normal secondary containment ventilation system and initiated the Standby Gas Treatment System. | The test was initiated through the_use of permanently installed test switches which simultaneously isolated the normal secondary containment ventilation system and initiated the Standby Gas Treatment System. | ||
- Review and approval by the Boston Edison Company's Nuclear Engineering l- | |||
: Department of the acceptance criteria of this test-ensures that! satisfactory results from its performance verifies the integrity of secondary containment. | |||
The data obtained during the test is enclosed.- | |||
Very truly yours, W. ~ D. Harrington PF6: caw | Very truly yours, W. ~ D. Harrington PF6: caw | ||
( | ( | ||
: Attachment Courtesy Copy to:- Director, Division of Project and Resident Programs Region I | : Attachment Courtesy Copy to:- Director, Division of Project and Resident Programs Region I U.S. Nuclear Regulatory Commission i | ||
U.S. Nuclear Regulatory Commission | g stiMPJMj8g_ | ||
k i | |||
P. | |||
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Latest revision as of 00:48, 13 December 2024
| ML20112F823 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 01/08/1985 |
| From: | Harrington W BOSTON EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20112F826 | List: |
| References | |
| #85-002, #85-2, NUDOCS 8501160055 | |
| Download: ML20112F823 (1) | |
Text
,_. _ _ _ - -.
SOSTON EDISON COMPANY 800 BovLaTON STREET BOSTON. MASSACHUSETTS 02199 wtLLIAM O. HARRINGTON January 8, 1985 BEco Ltr. #85-002
""* =
Director. 0ffice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
. Washington, D.C.
20555 ATTN: Document Control Desk Docket Nuncer 50-293 License DPR-35
Subject:
Secondary Containment Leak Rate Test Report
Dear Sir:
A Secondary Containment Leak Rate Test (8.7.3) was satisfactorily performed on October 28, 1984 and is hereby reported as required by PNPS Technical
-Specification 6.9.C.3.
This test was performed to verify secondary containment integrity at Refueling Outage #6 prior to refuel.
This secondary containment leak rate test demonstrated that the Standby Gas
' Treatment System (SGTS) was capable of maintaining greater than 1/4 inch of water vacuum in the secondary containment, as required by PNPS Technical Specification 4.7.C.1.c.
The test was initiated through the_use of permanently installed test switches which simultaneously isolated the normal secondary containment ventilation system and initiated the Standby Gas Treatment System.
- Review and approval by the Boston Edison Company's Nuclear Engineering l-
- Department of the acceptance criteria of this test-ensures that! satisfactory results from its performance verifies the integrity of secondary containment.
The data obtained during the test is enclosed.-
Very truly yours, W. ~ D. Harrington PF6: caw
(
- Attachment Courtesy Copy to:- Director, Division of Project and Resident Programs Region I U.S. Nuclear Regulatory Commission i
g stiMPJMj8g_
k i
P.
. _ _ _.. _ _ _. _... ~.,.. ~ _.. _, _ _. _ _