ML18058B965: Difference between revisions
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| issue date = 07/17/1992 | | issue date = 07/17/1992 | ||
| title = Responds to NRC 920103 SER of Inservice Testing Program Relief Requests.Advises That Relief Request PV-36 Re Increase in Stroke Time from Ref Value Instead of Stroke Time of Previous Test Implemented at Facilities | | title = Responds to NRC 920103 SER of Inservice Testing Program Relief Requests.Advises That Relief Request PV-36 Re Increase in Stroke Time from Ref Value Instead of Stroke Time of Previous Test Implemented at Facilities | ||
| author name = | | author name = Baron R | ||
| author affiliation = TENNESSEE VALLEY AUTHORITY | | author affiliation = TENNESSEE VALLEY AUTHORITY | ||
| addressee name = | | addressee name = | ||
| Line 13: | Line 13: | ||
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | ||
| page count = 2 | | page count = 2 | ||
| project = | | project = TAC:M82118, TAC:M82119, TAC:M82120 | ||
| stage = Request | | stage = Request | ||
}} | }} | ||
| Line 19: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter:r. | {{#Wiki_filter:r. | ||
* i Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609 JUL 17 1992 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: | * i Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609 JUL 17 1992 U.S. Nuclear Regulatory Commission ATTN: | ||
In the Matter of Tennessee Valley Authority ) ) Docket Nos. 50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) -RESPONSE TO NRC SAFETY EVALUATION REPORT (SER) DATED JANUARY 3, 1992 -INSERVICE TESTING PROGRAM | Document Control Desk Washington, D.C. | ||
20555 Gentlemen: | |||
In the Matter of Tennessee Valley Authority | |||
) | |||
) | |||
Docket Nos. 50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - RESPONSE TO NRC SAFETY EVALUATION REPORT (SER) DATED JANUARY 3, 1992 - INSERVICE TESTING PROGRAM | |||
==Reference:== | ==Reference:== | ||
: 1. Letter from TVA to NRC dated November 5, 1992, "Browns Ferry Nuclear Plant (BFN) -American Society of Mechanical Engineers (ASME) Section XI -Pump and Valve Testing Program, Request for Relief" 2. Safety Evaluation Report (SER) from NRC to TVA dated January 3, 1992, "Inservice Testing Program Relief for the Browns Ferry Nuclear Plant (TAC Nos. M82118, M82119, and M82120)" Reference 1 requested relief from the corrective action requirements of ASME Code XI, Paragraph IWV-3417(a) for all valves in the !ST program. Reference 1 proposed that corrective actions limits be based on an increase in stroke time from a reference value instead of the stroke time of the previous test. The Request for Release is documented by PV-36 of the BFN Pump and Valve Program. Reference 2 provides approval of the proposed alternate method requested in Reference | : 1. Letter from TVA to NRC dated November 5, 1992, "Browns Ferry Nuclear Plant (BFN) - American Society of Mechanical Engineers (ASME) Section XI - Pump and Valve Testing Program, Request for Relief" | ||
: 2. | |||
The purpose of this letter is to provide notification that PV-36 has been implemented at BFN. | Safety Evaluation Report (SER) from NRC to TVA dated January 3, 1992, "Inservice Testing Program Relief for the Browns Ferry Nuclear Plant (TAC Nos. M82118, M82119, and M82120)" | ||
0500025q ppR_ p | Reference 1 requested relief from the corrective action requirements of ASME Code XI, Paragraph IWV-3417(a) for all valves in the !ST program. | ||
.. \ | Reference 1 proposed that corrective actions limits be based on an increase in stroke time from a reference value instead of the stroke time of the previous test. The Request for Release is documented by PV-36 of the BFN Pump and Valve Program. | ||
Reference 2 provides approval of the proposed alternate method requested in Reference 1. | |||
In addition, Reference 2 requested BFN to notify the staff when PV-36 was implemented. | |||
The purpose of this letter is to provide notification that PV-36 has been implemented at BFN. | |||
5 920717 qp* 2DOR724AOD01t~ 0500025q ppR_ | |||
p | |||
~.. \\ | |||
2 U.S. Nuclear Regulatory Commission JUL 17 1992 If you have any questions, contact me at extension 205-729-7566. | |||
Sincerely, | Sincerely, | ||
* R. Baron Manager of Site Licensing cc: NRG Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323}} | * R. Baron Manager of Site Licensing cc: | ||
NRG Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323}} | |||
Latest revision as of 07:55, 6 January 2025
| ML18058B965 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/17/1992 |
| From: | Baron R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M82118, TAC-M82119, TAC-M82120, NUDOCS 9207240165 | |
| Download: ML18058B965 (2) | |
Text
r.
- i Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609 JUL 17 1992 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of Tennessee Valley Authority
)
)
Docket Nos. 50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - RESPONSE TO NRC SAFETY EVALUATION REPORT (SER) DATED JANUARY 3, 1992 - INSERVICE TESTING PROGRAM
Reference:
- 1. Letter from TVA to NRC dated November 5, 1992, "Browns Ferry Nuclear Plant (BFN) - American Society of Mechanical Engineers (ASME)Section XI - Pump and Valve Testing Program, Request for Relief"
- 2.
Safety Evaluation Report (SER) from NRC to TVA dated January 3, 1992, "Inservice Testing Program Relief for the Browns Ferry Nuclear Plant (TAC Nos. M82118, M82119, and M82120)"
Reference 1 requested relief from the corrective action requirements of ASME Code XI, Paragraph IWV-3417(a) for all valves in the !ST program.
Reference 1 proposed that corrective actions limits be based on an increase in stroke time from a reference value instead of the stroke time of the previous test. The Request for Release is documented by PV-36 of the BFN Pump and Valve Program.
Reference 2 provides approval of the proposed alternate method requested in Reference 1.
In addition, Reference 2 requested BFN to notify the staff when PV-36 was implemented.
The purpose of this letter is to provide notification that PV-36 has been implemented at BFN.
5 920717 qp* 2DOR724AOD01t~ 0500025q ppR_
p
~.. \\
2 U.S. Nuclear Regulatory Commission JUL 17 1992 If you have any questions, contact me at extension 205-729-7566.
Sincerely,
- R. Baron Manager of Site Licensing cc:
NRG Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35611 Mr. Thierry M. Ross, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323