ML18101A618: Difference between revisions

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{{#Wiki_filter:.**
{{#Wiki_filter:. **
Public Service Electric and Gas Company Joseph J. Hagan                   Public Service Electric and Gas Company     P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President* Nuclear Operations APR 041995 LR-N95011 United States Nuclear Regulatory Commission Docum.ent Control Desk Washington, DC 20555 Gentlemen:
Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President* Nuclear Operations APR 041995 LR-N95011 United States Nuclear Regulatory Commission Docum.ent Control Desk Washington, DC 20555 Gentlemen:
INSERVICE TESTING PROGRAM RELIEF REQUEST SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 Public Service Electric & Gas Company (PSE&G) hereby submits in Attachment 1 to this letter, a proposed revision to the Inservice Testing Program for saiem Generating Station, Units Nos. 1 and 2.
INSERVICE TESTING PROGRAM RELIEF REQUEST SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 Public Service Electric & Gas Company (PSE&G) hereby submits in to this letter, a proposed revision to the Inservice Testing Program for saiem Generating Station, Units Nos. 1 and 2.
This request is submitted in accordance with Section 4.0.5 of Appendix A to the Technical Specifications and the ASME Boiler and Pressure Vessel Code, Section XI.
This request is submitted in accordance with Section 4.0.5 of Appendix A to the Technical Specifications and the ASME Boiler and Pressure Vessel Code, Section XI. contains a proposed relief request for the 1(2)SJ3 Refueling Water Storage Tank to Suction of the Charging Safety Injection Pumps Check Valve.
Attachment 1 contains a proposed relief request for the 1(2)SJ3 Refueling Water Storage Tank to Suction of the Charging Safety Injection Pumps Check Valve. Basis for the relief and alternate testing are identified in this relief request.
Basis for the relief and alternate testing are identified in this relief request.
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
Sincerely,
(
(        9504100099 950404
9504100099 950404  
                ,PDR ADOCK 05000272
,PDR ADOCK 05000272  
              .P.                       PDR
.P.
PDR Sincerely,


APR 041995 Document.control Desk           2 LR-N95011 c   Mr. T. T. Martin, Administrator - Region I
Document.control Desk LR-N95011 2
: u. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager - Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 12E21 Rockville, MD 20852 Mr. c. Marschall - Salem (S09)
c Mr. T. T. Martin, Administrator - Region I
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Emanuel Mossa New Jersey Department of Labor and Industry PO Box 1503 Labor and Industry Building Trenton, NJ 08625
: u. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager -
Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 12E21 Rockville, MD 20852 Mr. c. Marschall -
Salem (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Emanuel Mossa New Jersey Department of Labor and Industry PO Box 1503 Labor and Industry Building Trenton, NJ 08625 APR 041995


LR~N95011 ATTACHMENT 1 RELIEF REQUEST
LR~N95011 ATTACHMENT 1 RELIEF REQUEST  


RELIEF REQUEST NUMBER: SC-SJ-V-1                                         PG. 1 OF2 COMPONENT:       Valves 1(2)SJ3 FUNCTION        Refueling Water Storage Tank (RWST) to suction of Charging Safety Injection Pumps check valve. This valve allows a flow path from RWST to the suction of the Charging Safety Injection Pumps. It also prevents backflow from the pump suction to the RWST during Containment Sump recirculation phase of emergency core cooling.
RELIEF REQUEST NUMBER: SC-SJ-V-1 PG. 1 OF2 COMPONENT:
CATEGORY:        C (check)
FUNCTION CATEGORY:
CLASS:          2 DRAWING NO.:    205234, SHT.1 (area of interest attached).
CLASS:
TEST REQUIREMENTS:       ASME Section XI, Subsection IWV-3520, (1983 edition, through the summer of 1983 addenda) requires that these valves be exercised every three months unless such testing is not practical during plant operation. In this case the valves may be exercised during cold shutdown.
DRAWING NO.:
BASIS FOR RELIEF         This valve cannot be full flow or partial flow exercised during plant operation since this would inject 2300 ppm boron into the Reactor Coolant System and cause a power transient. There is no recirculation flowpath back to the RWST available during plant operation ..
Valves 1(2)SJ3 Refueling Water Storage Tank (RWST) to suction of Charging Safety Injection Pumps check valve. This valve allows a flow path from RWST to the suction of the Charging Safety Injection Pumps. It also prevents backflow from the pump suction to the RWST during Containment Sump recirculation phase of emergency core cooling.
C (check) 2 205234, SHT.1 (area of interest attached).
TEST REQUIREMENTS:
ASME Section XI, Subsection IWV-3520, (1983 edition, through the summer of 1983 addenda) requires that these valves be exercised every three months unless such testing is not practical during plant operation. In this case the valves may be exercised during cold shutdown.
BASIS FOR RELIEF This valve cannot be full flow or partial flow exercised during plant operation since this would inject 2300 ppm boron into the Reactor Coolant System and cause a power transient. There is no recirculation flowpath back to the RWST available during plant operation..
This valve cannot be full flow exercised during cold shutdown because the discharge flow rate and pressure would challenge the Pressurizer Overpressure Protection System which is the Reactor Coolant System low temperature overpressure mitigation system. The valve will be part flow exercised open during cold shutdown using the normal charging flow path. Closed exercise will be verified by radiographing during cold shutdown following the partial flow open testing.
This valve cannot be full flow exercised during cold shutdown because the discharge flow rate and pressure would challenge the Pressurizer Overpressure Protection System which is the Reactor Coolant System low temperature overpressure mitigation system. The valve will be part flow exercised open during cold shutdown using the normal charging flow path. Closed exercise will be verified by radiographing during cold shutdown following the partial flow open testing.
The only practical positive means of verifying closed exercise for this valve at this time is to radiograph the valve. The line between the check valve and stop valves might be drained to insure closure, but there is no practical way to refill the section which had been drained.
The only practical positive means of verifying closed exercise for this valve at this time is to radiograph the valve. The line between the check valve and stop valves might be drained to insure closure, but there is no practical way to refill the section which had been drained.
Radiographing on a quarterly basis when the valve has not been repositioned would be burdensome with no corresponding increase in the margin of safety.
Radiographing on a quarterly basis when the valve has not been repositioned would be burdensome with no corresponding increase in the margin of safety.  


RELIEF REQUEST NUMBER: SC-SJ-V-1                                   PG. 2 OF 2 ALTERNATE TESTING   This valve will be part flow tested during cold shutdown. This valve will be full flow exercised open during the Charging Safety Injection flow balancing during refueling outages. This condition most closely approximates the Charging Safety Injection flows during a design basis large break loss of cooling accident.. The full flow exercise close verification will be done by radiography or other positive means of ensuring valve closure coincident with its full flow open exercise.
RELIEF REQUEST NUMBER: SC-SJ-V-1 PG. 2 OF 2 ALTERNATE TESTING This valve will be part flow tested during cold shutdown. This valve will be full flow exercised open during the Charging Safety Injection flow balancing during refueling outages. This condition most closely approximates the Charging Safety Injection flows during a design basis large break loss of cooling accident.. The full flow exercise close verification will be done by radiography or other positive means of ensuring valve closure coincident with its full flow open exercise.  


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Latest revision as of 01:21, 6 January 2025

Submits Request for Relief for 1(2)SJ3 Refueling Water Storage Tank to Suction of Charging Safety Injection Pumps Check Valve
ML18101A618
Person / Time
Site: Salem  
Issue date: 04/04/1995
From: Hagan J
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N95011, NUDOCS 9504100099
Download: ML18101A618 (6)


Text

. **

Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President* Nuclear Operations APR 041995 LR-N95011 United States Nuclear Regulatory Commission Docum.ent Control Desk Washington, DC 20555 Gentlemen:

INSERVICE TESTING PROGRAM RELIEF REQUEST SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 Public Service Electric & Gas Company (PSE&G) hereby submits in to this letter, a proposed revision to the Inservice Testing Program for saiem Generating Station, Units Nos. 1 and 2.

This request is submitted in accordance with Section 4.0.5 of Appendix A to the Technical Specifications and the ASME Boiler and Pressure Vessel Code,Section XI. contains a proposed relief request for the 1(2)SJ3 Refueling Water Storage Tank to Suction of the Charging Safety Injection Pumps Check Valve.

Basis for the relief and alternate testing are identified in this relief request.

Should there be any questions with regard to this submittal, please do not hesitate to contact us.

(

9504100099 950404

,PDR ADOCK 05000272

.P.

PDR Sincerely,

Document.control Desk LR-N95011 2

c Mr. T. T. Martin, Administrator - Region I

u. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager -

Salem U. s. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 12E21 Rockville, MD 20852 Mr. c. Marschall -

Salem (S09)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. Emanuel Mossa New Jersey Department of Labor and Industry PO Box 1503 Labor and Industry Building Trenton, NJ 08625 APR 041995

LR~N95011 ATTACHMENT 1 RELIEF REQUEST

RELIEF REQUEST NUMBER: SC-SJ-V-1 PG. 1 OF2 COMPONENT:

FUNCTION CATEGORY:

CLASS:

DRAWING NO.:

Valves 1(2)SJ3 Refueling Water Storage Tank (RWST) to suction of Charging Safety Injection Pumps check valve. This valve allows a flow path from RWST to the suction of the Charging Safety Injection Pumps. It also prevents backflow from the pump suction to the RWST during Containment Sump recirculation phase of emergency core cooling.

C (check) 2 205234, SHT.1 (area of interest attached).

TEST REQUIREMENTS:

ASME Section XI, Subsection IWV-3520, (1983 edition, through the summer of 1983 addenda) requires that these valves be exercised every three months unless such testing is not practical during plant operation. In this case the valves may be exercised during cold shutdown.

BASIS FOR RELIEF This valve cannot be full flow or partial flow exercised during plant operation since this would inject 2300 ppm boron into the Reactor Coolant System and cause a power transient. There is no recirculation flowpath back to the RWST available during plant operation..

This valve cannot be full flow exercised during cold shutdown because the discharge flow rate and pressure would challenge the Pressurizer Overpressure Protection System which is the Reactor Coolant System low temperature overpressure mitigation system. The valve will be part flow exercised open during cold shutdown using the normal charging flow path. Closed exercise will be verified by radiographing during cold shutdown following the partial flow open testing.

The only practical positive means of verifying closed exercise for this valve at this time is to radiograph the valve. The line between the check valve and stop valves might be drained to insure closure, but there is no practical way to refill the section which had been drained.

Radiographing on a quarterly basis when the valve has not been repositioned would be burdensome with no corresponding increase in the margin of safety.

RELIEF REQUEST NUMBER: SC-SJ-V-1 PG. 2 OF 2 ALTERNATE TESTING This valve will be part flow tested during cold shutdown. This valve will be full flow exercised open during the Charging Safety Injection flow balancing during refueling outages. This condition most closely approximates the Charging Safety Injection flows during a design basis large break loss of cooling accident.. The full flow exercise close verification will be done by radiography or other positive means of ensuring valve closure coincident with its full flow open exercise.

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