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{{#Wiki_filter:Q 0cll PA~+ CE ~+ 5 I p~~L= Qp3p       cg C~L Carolina Power 8 Light Company OEC   04   t987 SERIAL: NLS-87-270 United States Nuclear Regulatory Commission ATTEiNTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-000/LICEiVSE NO. NPF-63 IN-SERVICE PUMP AND VALVETESTING (IST) PROGRAM Gentlemen:
{{#Wiki_filter:C~L Carolina Power 8 Light Company Q 0cllPA~+ CE ~+ 5 I p~~L= Qp3p cg OEC 04 t987 SERIAL: NLS-87-270 United States Nuclear Regulatory Commission ATTEiNTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-000/LICEiVSE NO. NPF-63 IN-SERVICE PUMP AND VALVETESTING (IST) PROGRAM Gentlemen:
On October 30, 1987, Carolina Power R Light Company (CPRL) submitted a code relief request regarding testing of the Reactor Coolant System (RCS) vent valves during refueling rather than quarterly. Based on further review, CPRL has determined that these valves can be tested on a cold shutdown basis. Therefore, CPRL herein rescinds the October 30, 1987 relief request and submits as a supplement to Revision 3 of the IST program, the attached "cold shutdown justification" to support testing the vent valves at cold shutdown. It is CPdcL's intent to incorporate this change into the IST program, effective December 22, 1987. Thereafter, the valves willbe tested in accordance with ASME Code requirements at cold shutdown [Ref. IWV-3~10 and IWV-3012 (a)]. The attached cold shutdown justification is provided for your review.
On October 30, 1987, Carolina Power R Light Company (CPRL) submitted a code relief request regarding testing of the Reactor Coolant System (RCS) vent valves during refueling rather than quarterly.
The RCS High Point Vents are required by NUREG-0737, "Clarification of TMI Action Plan Requirements, Item II.B.I n As required by NUREG 0737, these valves provide a means to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation. The scenarios for which these valves would be used are beyond the design basis of the plant. Use of these valves is covered by emergency operating procedures as required by NUREG-0737. Also, as required by NUREG-0737, the vents must not lead to an unacceptable increase in the probability of a loss-of-coolant accident and must be designed to ensure a low probability of inadvertent or irreversible actuation. The SHNPP design (refer to attached Figure) consists of six solenoid-actuated, pilot-operated valves. The valves are normally closed and provide a double RCS barrier. The valves vent to the containment or the Pressurizer Relief Tank (PRT). The only routine use of the valves occurs during filland vent of the RCS.
Based on further review, CPRL has determined that these valves can be tested on a cold shutdown basis.
Technical Specification 3.0.11 requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation. Technical Specification 0.0.11.2.a requires testing of the vent valves every 18 months. The In-service Testing program required by Technical Specification 0.0.5 requires testing of these valves quarterly. Testing of the valves with the RGS pressurized could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage during
Therefore, CPRL herein rescinds the October 30, 1987 relief request and submits as a supplement to Revision 3 of the IST program, the attached "cold shutdown justification" to support testing the vent valves at cold shutdown. It is CPdcL's intent to incorporate this change into the IST program, effective December 22, 1987. Thereafter, the valves willbe tested in accordance with ASME Code requirements at cold shutdown [Ref. IWV-3~10 and IWV-3012 (a)]. The attached cold shutdown justification is provided for your review.
.testing. -The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resultin i         utdown.
The RCS High Point Vents are required by NUREG-0737, "Clarification of TMIAction Plan Requirements, Item II.B.I n As required by NUREG 0737, these valves provide a means to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation. The scenarios for which these valves would be used are beyond the design basis of the plant.
o4't 41t FayettOWtte Street ~ P. O. BOX 1551 ~ Ratergn, N. C. 27602 lh
Use of these valves is covered by emergency operating procedures as required by NUREG-0737. Also, as required by NUREG-0737, the vents must not lead to an unacceptable increase in the probability of a loss-of-coolant accident and must be designed to ensure a low probability of inadvertent or irreversible actuation.
The SHNPP design (refer to attached Figure) consists of six solenoid-actuated, pilot-operated valves.
The valves are normally closed and provide a double RCS barrier.
The valves vent to the containment or the Pressurizer Relief Tank (PRT). The only routine use of the valves occurs during filland vent of the RCS.
Technical Specification 3.0.11 requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation.
Technical Specification 0.0.11.2.a requires testing of the vent valves every 18 months.
The In-service Testing program required by Technical Specification 0.0.5 requires testing of these valves quarterly.
Testing of the valves with the RGS pressurized could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage during
.testing. -The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resultin i
utdown.
41t FayettOWtte Street
~ P. O. BOX 1551
~ Ratergn, N. C. 27602 o4't lh


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Testing at power (i.e., with the RCS pressurized) has demonstrated that a scenario exists by which the block valves can be forced open during testing of the upstream vent valve(s). This is due to a combination of valve test sequencing, timing, and the particular characteristics of the valve's fluid-assisted operation.
Testing at power (i.e., with the RCS pressurized) has demonstrated that a scenario exists by which the block valves can be forced open during testing of the upstream vent valve(s).
This scenario has been addressed by an orientation change of the block valves and changes in the test procedure. These changes will improve the reliability of these valves by: 1) reducing the time necessary to fully reseat the valve discs and 2) by not challenging the valves before the discs are fully reseated.
This is due to a combination of valve test sequencing, timing, and the particular characteristics of the valve's fluid-assisted operation.
Given that these valves are not assumed to operate in design basis accidents and the potential consequences of testing them at full system pressure, testing of these valves at power is contrary to both the goal of maintaining double isolation of the RCS and the NUREG-0737 requirement to ensure a low probability of inadvertent or irreversible actuation of the valves. For the above reasons, testing these valves in Modes 1-0 is impractical.
This scenario has been addressed by an orientation change of the block valves and changes in the test procedure.
N If you have any questions please contact Steven D. Chaplin   at (919) 836-6623.
These changes willimprove the reliability of these valves by:
Yours very truly, S.. Zi me.man nage.
: 1) reducing the time necessary to fullyreseat the valve discs and 2) by not challenging the valves before the discs are fullyreseated.
Nuclear Licensing Section SDC/bmc      (5307SDC)
Given that these valves are not assumed to operate in design basis accidents and the potential consequences of testing them at fullsystem pressure, testing of these valves at power is contrary to both the goal of maintaining double isolation of the RCS and the NUREG-0737 requirement to ensure a low probability of inadvertent or irreversible actuation of the valves.
Attachment cc:   Mr. B. C. Buckley Dr. 3. Nelson Grace Mr. G. F. Maxwell
For the above reasons, testing these valves in Modes 1-0 is impractical.
NIf you have any questions please contact Steven D. Chaplin at (919) 836-6623.
Yours very truly, SDC/bmc (5307SDC)
Attachment S.. Zi me.man nage.
Nuclear Licensing Section cc:
Mr. B. C. Buckley Dr. 3. Nelson Grace Mr. G. F. Maxwell


COLD SHUTDOWN TEST 3USTIFICATION System:            Reactor Coolant CS-2 Valves:            IRC-900, 90l, 902, 903, 900, 905 Category:          B Class:
System:
Function:          RCS Vent Valves Test Requirement:  Exercise valve for operability, observe proper operation of fa!1-safe actuator and measure stroke time quarterly.
Valves:
Cold Shutdown      VaLves are RCS High Point Vent Valves, which were installed in Justification:      response to NUREG 0737, Item II.B.L and are designed onlv to vent noncondensible gas produced by a "beyond design basis accident" from the RCS. These valves are only routinely used during cold shutdown to provide a path for normal RCS venting prior to heatup.
Category:
Class:
Function:
Test Requirement:
Cold Shutdown Justification:
COLD SHUTDOWN TEST 3USTIFICATION Reactor Coolant CS-2 IRC-900, 90l, 902, 903, 900, 905 B
RCS Vent Valves Exercise valve for operability, observe proper operation of fa!1-safe actuator and measure stroke time quarterly.
VaLves are RCS High Point Vent Valves, which were installed in response to NUREG 0737, Item II.B.L and are designed onlv to vent noncondensible gas produced by a "beyond design basis accident" from the RCS.
These valves are only routinely used during cold shutdown to provide a path for normal RCS venting prior to heatup.
Technical Specification 3.0.LL requires that one vent path from
Technical Specification 3.0.LL requires that one vent path from
                  -
- the reactor pressure vessel head and one vent path from the pressurize.
the reactor pressure vessel head and one vent path from the pressurize. be ope.able and closed durin~ ope.ation. Technical Specifications requires testing oi the vent valves every LS months. Testing oi the valves during power ope.ations could result in a, limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage. The result would be a, loss of RCS inventory to the pressurize. relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resulting in unit shutdown.
be ope.able and closed durin~ ope.ation.
Quarterly Part     None. These valves are not equipped with part stroke Stroke Testing:    exerciser s.
Technical Specifications requires testing oi the vent valves every LS months.
Alternate Test:     Exercise valve for operability, observe proper operation of fail-safe actuators, and measure stroke time during a cold shutdown, if not performed within the previous 92 days.
Testing oi the valves during power ope.ations could result in a, limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage.
The result would be a, loss of RCS inventory to the pressurize. relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resulting in unit shutdown.
Quarterly Part Stroke Testing:
None.
These valves are not equipped with part stroke exerciser s.
Alternate Test:
Exercise valve for operability, observe proper operation of fail-safe actuators, and measure stroke time during a cold shutdown, if not performed within the previous 92 days.
(5347SDC/bmc)
(5347SDC/bmc)


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REGUL*     Y INFORMATION DISTR IBUTIO       YSTEM (RIDS)
Y INFORMATION DISTR IBUTIO YSTEM (RIDS)
V~'CCESSION NBR: 8712110047       DOC. DATE: 87/12/04       NOTARIZED: NO       DOCKET 0 FACIL:   50-400           Shearon Harv is Nuclear   Power   Planti Unit ii Carolina   05000400 AUTH. NAME                     AUTHOR AFF ILlATION ZIMMERMANiS. R.                 Carolina Power 5 Light Co.
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RECIP. NAME                     RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
V~'CCESSION NBR: 8712110047 DOC. DATE: 87/12/04 NOTARIZED:
NO FACIL: 50-400 Shearon Harv is Nuclear Power Planti Unit ii Carolina AUTH. NAME AUTHOR AFFILlATION ZIMMERMANiS. R.
Carolina Power 5 Light Co.
RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Forwards cold shutdown     test gustification submitted as supl to Rev 3 of   in-service   pump 8a valve testing program to support testing vent     valves   at   cold shutdown.
Forwards cold shutdown test gustification submitted as supl to Rev 3 of in-service pump 8a valve testing program to support testing vent valves at cold shutdown.
DISTRIBUTION CODE: A047D                 COPIES RECEIVED: LTR         ENCL j   SIZE:
DISTRIBUTION CODE:
TITLE:         OR     Submittal: Inservice Inspection/Testing 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             5     5 BUCKLEY'S B            1    1 INTERNAL: AEOD/DOA                           1     1       AEOD/DSP/TPAB         1 ARM/DAF/LFMB                  0       .NRR/DEST/MEB NRR/DEST/MTB OGC/HDSi 1
A047D COPIES RECEIVED: LTR ENCL j
SIZE:
TITLE:
OR Submittal:
Inservice Inspection/Testing NOTES: Application for permit renewal filed.
DOCKET 0 05000400 05000400 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY'S B COPIES LTTR ENCL 1
0 1
1 RECIPIENT ID CODE/NAME PD2-1 PD COPIES LTTR ENCL 5
5 INTERNAL: AEOD/DOA ARM/DAF/LFMB NRR/DEST/MTB OGC/HDSi RES/DE/EIB 1
1 AEOD/DSP/TPAB 1
0
.NRR/DEST/MEB 1
1, NRR/PMAS/ ILRB 1
0 01 1
1 1
1 1
1, 0
NRR/PMAS/ ILRB 01 1
1 1
1 1
1 RES/DE/EIB              1    1 EXTERNAL: LPDR                               1     1       NRC PDR               1    1 NSIC                    1     1 TOTAL NUMBER OF COPIES REQUIRED: LTTR                       19   ENCL   ih
1 1
EXTERNAL:
LPDR NSIC 1
1 1
1 NRC PDR 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 19 ENCL ih


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SRK Carolina Power & Light Company DEC   04 $ 87 SERIAL: NLS-87-270 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-000/LICENSE NO. NPF-63 IN-SERVICE PUMP AND VALVE TESTING (IST) PROGRAM Gentlemen:
~
On October 30, 1987, Carolina Power           4 Light Company (CPRL) submitted           a code relief request regarding testing of the Reactor Coolant System (RCS) vent valves during refueling rather than quarterly. Based on further review, CPRL has determined that these valves can be tested on a cold shutdown basis. Therefore, CPRL herein rescinds the October 30, 1987 relief request and submits as a supplement to Revision 3 of the IST program, the attached "cold shutdown justification" to support testing the vent valves at cold shutdown. It is CPRL's intent to incorporate this change into the IST program, effective December 22, 1987. Thereafter, the valves will be tested in accordance with ASME Code requirements at cold shutdown [Ref. IWV-3010 and IWV-3012 (a)]. The attached cold shutdown justification is provided for your review.
SRK Carolina Power & Light Company DEC 04 $87 SERIAL: NLS-87-270 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-000/LICENSE NO. NPF-63 IN-SERVICE PUMP AND VALVETESTING (IST) PROGRAM Gentlemen:
The RCS High Point Vents are required by NUREG-0737, "Clarification of TMI Action Plan Requirements, Item II.B.1." As required by NUREG 0737, these valves provide a means to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation. The scenarios for which these valves would be used are beyond the design basis of the plant. Use of these valves is covered by emergency operating procedures as required by NUREG-0737. Also, as required by NUREG-0737, the vents must not lead to an unacceptable increase in the probability of a loss-of-coolant accident and must be designed to ensure a low probability of inadvertent or irreversible actuation. The SHNPP design (refer to attached Figure) consists of six solenoid-actuated, pilot-operated valves. The valves are normally closed and provide a double RCS barrier. The valves vent to the containment or the Pressurizer Relief Tank (PRT). The only routine use of the valves occurs during filland vent of the RCS.
On October 30, 1987, Carolina Power 4 Light Company (CPRL) submitted a code relief request regarding testing of the Reactor Coolant System (RCS) vent valves during refueling rather than quarterly.
Technical Specification 3.0.11 requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation. Technical Specification 0.0.11.2.a requires testing of the vent valves every 18 months. The In-service Testing program required by Technical Specification 0.0.5 requires testing of these valves quarterly. Testing of the valves with the RCS pressurized could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage during testing. The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resulting in unit shutdown.
Based on further review, CPRL has determined that these valves can be tested on a cold shutdown basis.
411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N, C. 27602 a712iioo47 87iao4 PDR   ADOCK   05000400 )
Therefore, CPRL herein rescinds the October 30, 1987 relief request and submits as a supplement to Revision 3 of the IST program, the attached "cold shutdown justification" to support testing the vent valves at cold shutdown. It is CPRL's intent to incorporate this change into the IST program, effective December 22, 1987. Thereafter, the valves willbe tested in accordance with ASME Code requirements at cold shutdown [Ref. IWV-3010 and IWV-3012 (a)]. The attached cold shutdown justification is provided for your review.
P                     PDR   LI
The RCS High Point Vents are required by NUREG-0737, "Clarification of TMIAction Plan Requirements, Item II.B.1." As required by NUREG 0737, these valves provide a means to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation. The scenarios for which these valves would be used are beyond the design basis of the plant.
Use of these valves is covered by emergency operating procedures as required by NUREG-0737.
Also, as required by NUREG-0737, the vents must not lead to an unacceptable increase in the probability of a loss-of-coolant accident and must be designed to ensure a low probability of inadvertent or irreversible actuation.
The SHNPP design (refer to attached Figure) consists of six solenoid-actuated, pilot-operated valves.
The valves are normally closed and provide a double RCS barrier.
The valves vent to the containment or the Pressurizer Relief Tank (PRT).
The only routine use of the valves occurs during filland vent of the RCS.
Technical Specification 3.0.11 requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation.
Technical Specification 0.0.11.2.a requires testing of the vent valves every 18 months.
The In-service Testing program required by Technical Specification 0.0.5 requires testing of these valves quarterly. Testing of the valves with the RCS pressurized could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage during testing.
The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resulting in unit shutdown.
411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N, C. 27602 a712iioo47 87iao4 PDR ADOCK 05000400 )
P PDR LI


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Testing at power (i.e., with the RCS pressurized) has demonstrated that a scenario exists by which the block valves can be forced open during testing of the upstream vent valve(s). This is due to a combination of valve test sequencing, timing, and the particular characteristics of the valve's fluid-assisted operation.
Testing at power (i.e., with the RCS pressurized) has demonstrated that a scenario exists by which the block valves can be forced open during testing of the upstream vent valve(s).
This scenario has been addressed by an orientation change of the block valves and changes in the test procedure. These changes will improve the reliability of these valves by: 1) reducing the time necessary to fully reseat the valve discs and 2) by not challenging the valves before the discs are fully reseated.
This is due to a combination of valve test sequencing, timing, and the particular characteristics of the valve's fluid-assisted operation.
Given that these valves are not assumed to operate in design basis accidents and the potential consequences of testing them at full system pressure, testing of these valves at power is contrary to both the goal of maintaining double isolation of the RCS and the NUREG-0737 requirement to ensure a low probability of inadvertent or irreversible actuation of the valves. For the above reasons, testing these valves in Modes I-0 is impractical.
This scenario has been addressed by an orientation change of the block valves and changes in the test procedure.
These changes willimprove the reliability of these valves by:
: 1) reducing the time necessary to fullyreseat the valve discs and 2) by not challenging the valves before the discs are fullyreseated.
Given that these valves are not assumed to operate in design basis accidents and the potential consequences of testing them at full system pressure, testing of these valves at power is contrary to both the goal of maintaining double isolation of the RCS and the NUREG-0737 requirement to ensure a low probability of inadvertent or irreversible actuation of the valves.
For the above reasons, testing these valves in Modes I-0 is impractical.
If you have any questions please contact Steven D. Chaplin at (919) 836-6623.
If you have any questions please contact Steven D. Chaplin at (919) 836-6623.
Yours very truly, S.. Zi merman nager Nuclear Licensing Section SDC/bmc      (5307SDC)
Yours very truly, SDC/bmc (5307SDC)
Attachment cc:     Mr. B. C. Buckley Dr. 3. Nelson Grace Mr. G. F. Maxwell
Attachment S.. Zi merman nager Nuclear Licensing Section cc:
Mr. B. C. Buckley Dr. 3. Nelson Grace Mr. G. F. Maxwell


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COLD SHUTDOWN TEST JUSTIFICATION System:             Reactor Coolant CS-2 Valves:             IRC-900, 90l, 902, 903, 900, 905 Category:
System:
Valves:
Category:
Class:
Class:
Function:           RCS Vent Valves Test Requirement:  Exercise valve for operability, observe proper operation of fail-safe actuator and measure stroke time quarterly.
Function:
Cold Shutdown,      Valves are RCS High Point Vent Valves, which were installed in Justification:      response to NUREG 0737, Item II.B.l and are designed ~onl to vent noncondensible gas produced by a "beyond design basis accident" from the RCS. These valves are only routinely used during cold shutdown to provide a path for normal RCS venting prior to heatup.
Test Requirement:
Technical Specification 3A.ll requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation. Technical Specifications requires testing of the vent valves every l8 months. Testing of the valves during power operations could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage. The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 34.6.2.d limits, possibly resulting in unit shutdown.
Cold Shutdown, Justification:
Quarterly Part     None. These valves are not equipped with part stroke Stroke Testing:    exerciser s.
COLD SHUTDOWN TEST JUSTIFICATION Reactor Coolant CS-2 IRC-900, 90l, 902, 903, 900, 905 RCS Vent Valves Exercise valve for operability, observe proper operation of fail-safe actuator and measure stroke time quarterly.
Alternate Test:    'Exercise valve for operability, observe proper operation of fail-safe actuators, and measure stroke time during a cold shutdown, if not performed within the previous 92 days.
Valves are RCS High Point Vent Valves, which were installed in response to NUREG 0737, Item II.B.l and are designed
~onl to vent noncondensible gas produced by a "beyond design basis accident" from the RCS.
These valves are only routinely used during cold shutdown to provide a path for normal RCS venting prior to heatup.
Technical Specification 3A.ll requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation.
Technical Specifications requires testing of the vent valves every l8 months.
Testing of the valves during power operations could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage.
The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 34.6.2.d limits, possibly resulting in unit shutdown.
Quarterly Part Stroke Testing:
Alternate Test:
None.
These valves are not equipped with part stroke exerciser s.
'Exercise valve for operability, observe proper operation of fail-safe actuators, and measure stroke time during a cold shutdown, if not performed within the previous 92 days.
(5347SDC/bmc)
(5347SDC/bmc)


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Latest revision as of 07:14, 7 January 2025

Rescinds 871030 Relief Request & Forwards Cold Shutdown Justification as Rev 3 to Inservice Pump & Valve Testing Program to Support Vent Valve Testing.Valves Will Be Tested Per ASME Code Requirements.Valves in Modes 1-4 Impractical
ML18005A231
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 12/04/1987
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NLS-87-274, NUDOCS 8712110047
Download: ML18005A231 (14)


Text

C~L Carolina Power 8 Light Company Q 0cllPA~+ CE ~+ 5 I p~~L= Qp3p cg OEC 04 t987 SERIAL: NLS-87-270 United States Nuclear Regulatory Commission ATTEiNTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-000/LICEiVSE NO. NPF-63 IN-SERVICE PUMP AND VALVETESTING (IST) PROGRAM Gentlemen:

On October 30, 1987, Carolina Power R Light Company (CPRL) submitted a code relief request regarding testing of the Reactor Coolant System (RCS) vent valves during refueling rather than quarterly.

Based on further review, CPRL has determined that these valves can be tested on a cold shutdown basis.

Therefore, CPRL herein rescinds the October 30, 1987 relief request and submits as a supplement to Revision 3 of the IST program, the attached "cold shutdown justification" to support testing the vent valves at cold shutdown. It is CPdcL's intent to incorporate this change into the IST program, effective December 22, 1987. Thereafter, the valves willbe tested in accordance with ASME Code requirements at cold shutdown [Ref. IWV-3~10 and IWV-3012 (a)]. The attached cold shutdown justification is provided for your review.

The RCS High Point Vents are required by NUREG-0737, "Clarification of TMIAction Plan Requirements, Item II.B.I n As required by NUREG 0737, these valves provide a means to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation. The scenarios for which these valves would be used are beyond the design basis of the plant.

Use of these valves is covered by emergency operating procedures as required by NUREG-0737. Also, as required by NUREG-0737, the vents must not lead to an unacceptable increase in the probability of a loss-of-coolant accident and must be designed to ensure a low probability of inadvertent or irreversible actuation.

The SHNPP design (refer to attached Figure) consists of six solenoid-actuated, pilot-operated valves.

The valves are normally closed and provide a double RCS barrier.

The valves vent to the containment or the Pressurizer Relief Tank (PRT). The only routine use of the valves occurs during filland vent of the RCS.

Technical Specification 3.0.11 requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation.

Technical Specification 0.0.11.2.a requires testing of the vent valves every 18 months.

The In-service Testing program required by Technical Specification 0.0.5 requires testing of these valves quarterly.

Testing of the valves with the RGS pressurized could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage during

.testing. -The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resultin i

utdown.

41t FayettOWtte Street

~ P. O. BOX 1551

~ Ratergn, N. C. 27602 o4't lh

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Testing at power (i.e., with the RCS pressurized) has demonstrated that a scenario exists by which the block valves can be forced open during testing of the upstream vent valve(s).

This is due to a combination of valve test sequencing, timing, and the particular characteristics of the valve's fluid-assisted operation.

This scenario has been addressed by an orientation change of the block valves and changes in the test procedure.

These changes willimprove the reliability of these valves by:

1) reducing the time necessary to fullyreseat the valve discs and 2) by not challenging the valves before the discs are fullyreseated.

Given that these valves are not assumed to operate in design basis accidents and the potential consequences of testing them at fullsystem pressure, testing of these valves at power is contrary to both the goal of maintaining double isolation of the RCS and the NUREG-0737 requirement to ensure a low probability of inadvertent or irreversible actuation of the valves.

For the above reasons, testing these valves in Modes 1-0 is impractical.

NIf you have any questions please contact Steven D. Chaplin at (919) 836-6623.

Yours very truly, SDC/bmc (5307SDC)

Attachment S.. Zi me.man nage.

Nuclear Licensing Section cc:

Mr. B. C. Buckley Dr. 3. Nelson Grace Mr. G. F. Maxwell

System:

Valves:

Category:

Class:

Function:

Test Requirement:

Cold Shutdown Justification:

COLD SHUTDOWN TEST 3USTIFICATION Reactor Coolant CS-2 IRC-900, 90l, 902, 903, 900, 905 B

RCS Vent Valves Exercise valve for operability, observe proper operation of fa!1-safe actuator and measure stroke time quarterly.

VaLves are RCS High Point Vent Valves, which were installed in response to NUREG 0737, Item II.B.L and are designed onlv to vent noncondensible gas produced by a "beyond design basis accident" from the RCS.

These valves are only routinely used during cold shutdown to provide a path for normal RCS venting prior to heatup.

Technical Specification 3.0.LL requires that one vent path from

- the reactor pressure vessel head and one vent path from the pressurize.

be ope.able and closed durin~ ope.ation.

Technical Specifications requires testing oi the vent valves every LS months.

Testing oi the valves during power ope.ations could result in a, limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage.

The result would be a, loss of RCS inventory to the pressurize. relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resulting in unit shutdown.

Quarterly Part Stroke Testing:

None.

These valves are not equipped with part stroke exerciser s.

Alternate Test:

Exercise valve for operability, observe proper operation of fail-safe actuators, and measure stroke time during a cold shutdown, if not performed within the previous 92 days.

(5347SDC/bmc)

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V~'CCESSION NBR: 8712110047 DOC. DATE: 87/12/04 NOTARIZED:

NO FACIL: 50-400 Shearon Harv is Nuclear Power Planti Unit ii Carolina AUTH. NAME AUTHOR AFFILlATION ZIMMERMANiS. R.

Carolina Power 5 Light Co.

RECIP. NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards cold shutdown test gustification submitted as supl to Rev 3 of in-service pump 8a valve testing program to support testing vent valves at cold shutdown.

DISTRIBUTION CODE:

A047D COPIES RECEIVED: LTR ENCL j

SIZE:

TITLE:

OR Submittal:

Inservice Inspection/Testing NOTES: Application for permit renewal filed.

DOCKET 0 05000400 05000400 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY'S B COPIES LTTR ENCL 1

0 1

1 RECIPIENT ID CODE/NAME PD2-1 PD COPIES LTTR ENCL 5

5 INTERNAL: AEOD/DOA ARM/DAF/LFMB NRR/DEST/MTB OGC/HDSi RES/DE/EIB 1

1 AEOD/DSP/TPAB 1

0

.NRR/DEST/MEB 1

1, NRR/PMAS/ ILRB 1

0 01 1

1 1

1 1

1 1

EXTERNAL:

LPDR NSIC 1

1 1

1 NRC PDR 1

1 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 19 ENCL ih

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SRK Carolina Power & Light Company DEC 04 $87 SERIAL: NLS-87-270 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-000/LICENSE NO. NPF-63 IN-SERVICE PUMP AND VALVETESTING (IST) PROGRAM Gentlemen:

On October 30, 1987, Carolina Power 4 Light Company (CPRL) submitted a code relief request regarding testing of the Reactor Coolant System (RCS) vent valves during refueling rather than quarterly.

Based on further review, CPRL has determined that these valves can be tested on a cold shutdown basis.

Therefore, CPRL herein rescinds the October 30, 1987 relief request and submits as a supplement to Revision 3 of the IST program, the attached "cold shutdown justification" to support testing the vent valves at cold shutdown. It is CPRL's intent to incorporate this change into the IST program, effective December 22, 1987. Thereafter, the valves willbe tested in accordance with ASME Code requirements at cold shutdown [Ref. IWV-3010 and IWV-3012 (a)]. The attached cold shutdown justification is provided for your review.

The RCS High Point Vents are required by NUREG-0737, "Clarification of TMIAction Plan Requirements, Item II.B.1." As required by NUREG 0737, these valves provide a means to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation. The scenarios for which these valves would be used are beyond the design basis of the plant.

Use of these valves is covered by emergency operating procedures as required by NUREG-0737.

Also, as required by NUREG-0737, the vents must not lead to an unacceptable increase in the probability of a loss-of-coolant accident and must be designed to ensure a low probability of inadvertent or irreversible actuation.

The SHNPP design (refer to attached Figure) consists of six solenoid-actuated, pilot-operated valves.

The valves are normally closed and provide a double RCS barrier.

The valves vent to the containment or the Pressurizer Relief Tank (PRT).

The only routine use of the valves occurs during filland vent of the RCS.

Technical Specification 3.0.11 requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation.

Technical Specification 0.0.11.2.a requires testing of the vent valves every 18 months.

The In-service Testing program required by Technical Specification 0.0.5 requires testing of these valves quarterly. Testing of the valves with the RCS pressurized could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage during testing.

The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 3.0.6.2.d limits, possibly resulting in unit shutdown.

411 Fayettevilte Street o P. O. Box 1551 o Raleigh. N, C. 27602 a712iioo47 87iao4 PDR ADOCK 05000400 )

P PDR LI

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Testing at power (i.e., with the RCS pressurized) has demonstrated that a scenario exists by which the block valves can be forced open during testing of the upstream vent valve(s).

This is due to a combination of valve test sequencing, timing, and the particular characteristics of the valve's fluid-assisted operation.

This scenario has been addressed by an orientation change of the block valves and changes in the test procedure.

These changes willimprove the reliability of these valves by:

1) reducing the time necessary to fullyreseat the valve discs and 2) by not challenging the valves before the discs are fullyreseated.

Given that these valves are not assumed to operate in design basis accidents and the potential consequences of testing them at full system pressure, testing of these valves at power is contrary to both the goal of maintaining double isolation of the RCS and the NUREG-0737 requirement to ensure a low probability of inadvertent or irreversible actuation of the valves.

For the above reasons, testing these valves in Modes I-0 is impractical.

If you have any questions please contact Steven D. Chaplin at (919) 836-6623.

Yours very truly, SDC/bmc (5307SDC)

Attachment S.. Zi merman nager Nuclear Licensing Section cc:

Mr. B. C. Buckley Dr. 3. Nelson Grace Mr. G. F. Maxwell

'f p ll 4

f.~

J "

System:

Valves:

Category:

Class:

Function:

Test Requirement:

Cold Shutdown, Justification:

COLD SHUTDOWN TEST JUSTIFICATION Reactor Coolant CS-2 IRC-900, 90l, 902, 903, 900, 905 RCS Vent Valves Exercise valve for operability, observe proper operation of fail-safe actuator and measure stroke time quarterly.

Valves are RCS High Point Vent Valves, which were installed in response to NUREG 0737, Item II.B.l and are designed

~onl to vent noncondensible gas produced by a "beyond design basis accident" from the RCS.

These valves are only routinely used during cold shutdown to provide a path for normal RCS venting prior to heatup.

Technical Specification 3A.ll requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation.

Technical Specifications requires testing of the vent valves every l8 months.

Testing of the valves during power operations could result in a limited but uncontrolled blowdown should the associated upstream or downstream valve fail, inadvertently open, or experience excessive leakage.

The result would be a loss of RCS inventory to the pressurizer relief tank or containment atmosphere in excess of Technical Specification 34.6.2.d limits, possibly resulting in unit shutdown.

Quarterly Part Stroke Testing:

Alternate Test:

None.

These valves are not equipped with part stroke exerciser s.

'Exercise valve for operability, observe proper operation of fail-safe actuators, and measure stroke time during a cold shutdown, if not performed within the previous 92 days.

(5347SDC/bmc)

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