ML18009A856: Difference between revisions
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{{#Wiki_filter:ACCELERATED D.TRIBUTION DEMONSTRATION SYSTEM<i (4'EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9104100025 DOC.DATE: 91/04/04 NOTARIZED: | {{#Wiki_filter:ACCELERATED D. TRIBUTION DEMONSTRATION SYSTEM | ||
NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION FLOYD,S.D. | <i (4'EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) | ||
Carolina Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | ACCESSION NBR:9104100025 DOC.DATE: 91/04/04 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION FLOYD,S.D. Carolina Power 6 Light Co. | ||
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | |||
==SUBJECT:== | ==SUBJECT:== | ||
Forwards addi Request for Relief CVCS RV-3 from inservice pump 6 valve testing program to permit CVCS charging pump inlet header check valve to be partial stroke exercised at cold shutdown 6 full stroke exercised at refueling. | Forwards addi Request for Relief CVCS RV-3 from inservice pump 6 valve testing program to permit CVCS charging pump inlet header check valve to be partial stroke exercised at cold shutdown 6 full stroke exercised at refueling. | ||
DISTRIBUTION CODE: RO47D COPIES RECEIVED:LTR | DISTRIBUTION CODE: RO47D TITLE: OR COPIES RECEIVED:LTR Submittal: Inservice Inspection/Testa. g/Relief ENCL SIZE: | ||
Inservice Inspection/Testa. | Q from + | ||
g/Relief from ASME Code NOTES:Application for permit renewal filed.05000400 RECIPIENT ID CODE/NAME PD2-1 LA BECKER,D INTERNAL: ACRS NRR/DET/ECMB 9H NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: EGGG BROWN,B | ASME Code NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 0 PD2-1 PD 1 1 BECKER,D 2 2 INTERNAL: ACRS 6 6 AEOD/DSP/TPAB 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NUDOCS-ABSTRACT 1 1 OC ~EH 1 0 OGC/HDS1 1 0 G~~ 1 1 RES/DSIR/EIB 1 1 EXTERNAL: EGGG BROWN,B 1 1 EG&G RANSOME i C 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS: | ||
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! | ||
Document Control Desk Washington, DC 20555 | TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19 | ||
Carolina Power&Light Company (CP&L)hereby submits for review an additional relief request to the Shearon Harris Nuclear Power Plant (SHNPP)In-Service Testing (IST)Program as approved by NRC on September 29, 1988.The SHNPP IST program requires that check valve 1CS-294, in the refueling water storage tank supply line to the charging pumps supply header, be full flow tested at cold shutdown.(see Chemical&Volume Control System CVCS CS-5).Full flow testing would necessitate the injection of large quantities of borated water into the Reactor Coolant System (RCS).In the course of reviewing and implementing the IST program, | |||
Relief request CVCS RV-3 is similar to previously approved relief SI RV-1 with regard to the basis for not full flow testing at power or at cold shutdown, and is consistent with the basis for not partial flow testing at power as identified in the Technical Evaluation Report accompanying the IST program approval ment:ioned above.The Shearon Harris Nuclear Power Plant is now in a refueling outage.Check valve 1CS-294 can and will be full flow tested, without the potential of challenging the RCS pressure boundary, during this refueling outage.However, CP&L requests prompt NRC review and approval of this request so that a program conflict can be avoided should SHNPP experience a cold shutdown subsequent to this refueling out:age.Please refer any questions regarding this submittal to Mr.Steven Chaplin at (919)546-6623.SDF/SDC Attachment cc: Mr.R.A.Becker Mr.S.D.Ebneter Mr.J.E.Tedrow | SNK Carolina Power & Light Company SERIAL: NLS-91-077 APR O4 199] 10CFR50.55a United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 IN-SERVICE PUMP AND VALVE TESTING PROGRAM RELIEF REQUEST Gentlemen: | ||
V~ | Carolina Power & Light Company (CP&L) hereby submits for review an additional relief request to the Shearon Harris Nuclear Power Plant (SHNPP) | ||
In-Service Testing (IST) Program as approved by NRC on September 29, 1988. | |||
Verification of forward flow operability can only be performed by injecting RWST water into the RCS.While at power, the charging pumps have insufficient head to overcome normal RCS operating pressure for a full flow test.Partial stroke exercising while at power would adversely affect RCS boron concentration and could lead to a reactivity transient. | The SHNPP IST program requires that check valve 1CS-294, in the refueling water storage tank supply line to the charging pumps supply header, be full flow tested at cold shutdown. (see Chemical & Volume Control System CVCS CS-5). Full flow testing would necessitate the injection of large quantities of borated water into the Reactor Coolant System (RCS). | ||
Full, forward flow verification at cold shutdown could result in a cold overpressurization of the RCS.The only time that there is sufficient RCS expansion volume is during refueling while the reactor vessel head is removed.Alternate Testing: Valve will be partial stroke exercised at cold.shutdown and full stroke exercised at refueling. | In the course of reviewing and implementing the IST program, determined that implementation of the full flow cold shutdown testing of it was valve 1CS-294 could result in challenging the RCS Cold Overpressure Protection System since inadequate expansion volume exists in the RCS to accommodate full flow testing of the check valve. Therefore, the attached relief request (CVCS RV-3) identifies alternate testing for check valve 1CS-294, i.e., partial stroke exercising at cold shutdown and full stroke exercising at refueling. Relief request CVCS RV-3 is similar to previously approved relief SI RV-1 with regard to the basis for not full flow testing at power or at cold shutdown, and is consistent with the basis for not partial flow testing at power as identified in the Technical Evaluation Report accompanying the IST program approval ment:ioned above. | ||
k tq}} | The Shearon Harris Nuclear Power Plant is now in a refueling outage. Check valve 1CS-294 can and will be full flow tested, without the potential of challenging the RCS pressure boundary, during this refueling outage. | ||
However, CP&L requests prompt NRC review and approval of this request so that a program conflict can be avoided should SHNPP experience a cold shutdown subsequent to this refueling out:age. | |||
Please refer any questions regarding this submittal to Mr. Steven Chaplin at (919) 546-6623. | |||
Yours very truly, | |||
~3 K+'anager Nuclear Licensing Section SDF/SDC Attachment cc: Mr. R. A. Becker Mr. S. D. Ebneter Mr. J. E. Tedrow 411 Fayettevitte Street o P. O. Box 1551 o Raleigh, N. C. 27602 9i04i0002S 9i0404 PDR ADOCK 05000400 i P PDR Q)' | |||
~ | |||
V~ | |||
Enclosure to NLS-91-077 RV-3 System: CVCS Valve: 1CS-294 Category: | |||
Class: | |||
Function: RWST Line to CVCS Charging Pump Inlet Header Check Valve Test Requirement: Verify forward flow operability. | |||
Basis for Relief: Verification of forward flow operability can only be performed by injecting RWST water into the RCS. While at power, the charging pumps have insufficient head to overcome normal RCS operating pressure for a full flow test. Partial stroke exercising while at power would adversely affect RCS boron concentration and could lead to a reactivity transient. | |||
Full, forward flow verification at cold shutdown could result in a cold overpressurization of the RCS. The only time that there is sufficient RCS expansion volume is during refueling while the reactor vessel head is removed. | |||
Alternate Testing: Valve will be partial stroke exercised at cold | |||
.shutdown and full stroke exercised at refueling. | |||
k | |||
tq}} | |||
Revision as of 05:34, 22 October 2019
| ML18009A856 | |
| Person / Time | |
|---|---|
| Site: | Harris |
| Issue date: | 04/04/1991 |
| From: | Floyd S CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-91-077, NLS-91-77, NUDOCS 9104100025 | |
| Download: ML18009A856 (4) | |
Text
ACCELERATED D. TRIBUTION DEMONSTRATION SYSTEM
<i (4'EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9104100025 DOC.DATE: 91/04/04 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION FLOYD,S.D. Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards addi Request for Relief CVCS RV-3 from inservice pump 6 valve testing program to permit CVCS charging pump inlet header check valve to be partial stroke exercised at cold shutdown 6 full stroke exercised at refueling.
DISTRIBUTION CODE: RO47D TITLE: OR COPIES RECEIVED:LTR Submittal: Inservice Inspection/Testa. g/Relief ENCL SIZE:
Q from +
ASME Code NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 0 PD2-1 PD 1 1 BECKER,D 2 2 INTERNAL: ACRS 6 6 AEOD/DSP/TPAB 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NUDOCS-ABSTRACT 1 1 OC ~EH 1 0 OGC/HDS1 1 0 G~~ 1 1 RES/DSIR/EIB 1 1 EXTERNAL: EGGG BROWN,B 1 1 EG&G RANSOME i C 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 19
SNK Carolina Power & Light Company SERIAL: NLS-91-077 APR O4 199] 10CFR50.55a United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 IN-SERVICE PUMP AND VALVE TESTING PROGRAM RELIEF REQUEST Gentlemen:
Carolina Power & Light Company (CP&L) hereby submits for review an additional relief request to the Shearon Harris Nuclear Power Plant (SHNPP)
In-Service Testing (IST) Program as approved by NRC on September 29, 1988.
The SHNPP IST program requires that check valve 1CS-294, in the refueling water storage tank supply line to the charging pumps supply header, be full flow tested at cold shutdown. (see Chemical & Volume Control System CVCS CS-5). Full flow testing would necessitate the injection of large quantities of borated water into the Reactor Coolant System (RCS).
In the course of reviewing and implementing the IST program, determined that implementation of the full flow cold shutdown testing of it was valve 1CS-294 could result in challenging the RCS Cold Overpressure Protection System since inadequate expansion volume exists in the RCS to accommodate full flow testing of the check valve. Therefore, the attached relief request (CVCS RV-3) identifies alternate testing for check valve 1CS-294, i.e., partial stroke exercising at cold shutdown and full stroke exercising at refueling. Relief request CVCS RV-3 is similar to previously approved relief SI RV-1 with regard to the basis for not full flow testing at power or at cold shutdown, and is consistent with the basis for not partial flow testing at power as identified in the Technical Evaluation Report accompanying the IST program approval ment:ioned above.
The Shearon Harris Nuclear Power Plant is now in a refueling outage. Check valve 1CS-294 can and will be full flow tested, without the potential of challenging the RCS pressure boundary, during this refueling outage.
However, CP&L requests prompt NRC review and approval of this request so that a program conflict can be avoided should SHNPP experience a cold shutdown subsequent to this refueling out:age.
Please refer any questions regarding this submittal to Mr. Steven Chaplin at (919) 546-6623.
Yours very truly,
~3 K+'anager Nuclear Licensing Section SDF/SDC Attachment cc: Mr. R. A. Becker Mr. S. D. Ebneter Mr. J. E. Tedrow 411 Fayettevitte Street o P. O. Box 1551 o Raleigh, N. C. 27602 9i04i0002S 9i0404 PDR ADOCK 05000400 i P PDR Q)'
~
V~
Enclosure to NLS-91-077 RV-3 System: CVCS Valve: 1CS-294 Category:
Class:
Function: RWST Line to CVCS Charging Pump Inlet Header Check Valve Test Requirement: Verify forward flow operability.
Basis for Relief: Verification of forward flow operability can only be performed by injecting RWST water into the RCS. While at power, the charging pumps have insufficient head to overcome normal RCS operating pressure for a full flow test. Partial stroke exercising while at power would adversely affect RCS boron concentration and could lead to a reactivity transient.
Full, forward flow verification at cold shutdown could result in a cold overpressurization of the RCS. The only time that there is sufficient RCS expansion volume is during refueling while the reactor vessel head is removed.
Alternate Testing: Valve will be partial stroke exercised at cold
.shutdown and full stroke exercised at refueling.
k
tq