L-11-287, 10 CFR 50.55a Request VR-1, Revision 1, Align Valve Testing Frequencies to NUREG-1482 Provision: Difference between revisions

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| issue date = 10/16/2011
| issue date = 10/16/2011
| title = 10 CFR 50.55a Request VR-1, Revision 1, Align Valve Testing Frequencies to NUREG-1482 Provision
| title = 10 CFR 50.55a Request VR-1, Revision 1, Align Valve Testing Frequencies to NUREG-1482 Provision
| author name = Bezilla M B
| author name = Bezilla M
| author affiliation = FirstEnergy Nuclear Operating Co
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:}}
{{#Wiki_filter:FENOC                                                                                        Perry Nuclear Power Plant 10 Center Road FirstEnergy Nuclear Operating Company                                                                  Perry, Ohio 44081 MarkB.Bezilla                                                                                              440-280-5382 Vice President                                                                                        Fax: 440-280-8029 October 16, 2011 L-11-287                                                                10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
 
==SUBJECT:==
 
Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 10 CFR 50.55a Request VR-1. Revision 1. Align Valve Testing Frequencies to NUREG-1482 Provision By correspondence dated May 19, 2011 (Accession No. ML111050267), the Nuclear Regulatory Commission (NRC) issued Amendment 156 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant (PNPP). The amendment modified the frequency of Surveillance Requirement (SR) 3.1.4.2 from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1."
Pursuant to 10 CFR 50.55a(a)(3), FirstEnergy Nuclear Operating Company (FENOC) is requesting NRC approval for a proposed alternative to certain requirements of the PNPP Inservice Testing Program (ISTP). Approval of the enclosed alternative would align the valve testing to the test frequencies in Technical Specification 3.1.4, "Control Rod Scram Times," making the ISTP consistent with NUREG-1482, "Guidelines for Inservice Testing at Nuclear Power Plants."
FENOC is requesting approval of the proposed alternative by March 2, 2012. The proposed alternative would be implemented prior to the March 10, 2012 scheduled date to perform SR 3.1.4.2 for control rod scram time testing.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil Lashley, Supervisor - Fleet Licensing, at (330) 315-6808.
Sincerely, Mark B. Bezilla
 
==Enclosure:==
 
Perry Nuclear Power Plant, 10 CFR 50.55a Request VR-1, Revision 1 cc:      NRC Region III Administrator NRC Resident Inspector
                ' NRC Project Manager
 
Perry Nuclear Power Plant 10 CFR 50.55a Request VR-1, Revision 1 Page 1 of 4 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
              -Alternative Provides Acceptable Level of Quality and Safety-
: 1. ASME Code Componentfs) Affected Category B Valves (Typical of 177) 1C11-126, Scram Inlet Valve (Class 2) 1C11-127, Scram Exhaust Valve (Class 2)
Category C Valves (Typical of 177) 1C11-114, Scram Discharge Header Check Valve (Class 2)
[OPEN direction only]
1C11-115, Charging Water Header Check Valve (Class 2)
[OPEN direction only]
These valves operate as an integral part of their respective hydraulic control unit (typical of 177) to rapidly insert the control rods into the core in support of the reactor scram function. Specifically:
Scram Inlet Valve (1C11-126) has a safety function to open and supply pressurized water to the bottom of the control rod drive piston to rapidly insert the control rod into the core.
Scram Exhaust Valve (1C11-127) has a safety function to open and vent water from above the control rod drive piston to the scram discharge header allowing control rod movement during the scram.
Scram Discharge Header Check Valve (1C11-114) has a safety function to close and prevent reverse flow from the scram discharge header back to the top of the control rod drive piston; during the scram, this check valve has a safety function to open and allow water from above the control rod drive piston to flow into the scram discharge header (with 1C11-127 open) allowing control rod movement.
Charging Water Header Check Valve (1C11-115) has a safety function to close and prevent the loss of water pressure in the event supply pressure to the scram accumulator is lost; during the scram, this check valve opens to allow flow to the bottom of the control rod drive piston (with 1C11-126 open).
 
Page 2 of 4
 
===2. Applicable Code Edition and Addenda===
American Society of Mechanical Engineers (ASME) OM Code-2001 Edition, Code for Operation and Maintenance of Nuclear Plants, with Addenda through OMb-2003.
: 3. Applicable Code Requirements ISTC-3510, Exercising Test Frequency states, "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520..."
ISTC-5131(a), Valve Stroke Testing states, "Active valves shall have their stroke times measured when exercised in accordance with ISTC-3500."
ISTC-5221(a), Valve Obturator Movement states, "The necessary valve obturator movement during exercising shall be demonstrated by performing both an open and a close test."
The Nuclear Regulatory Commission (NRC) approved an alternative to these requirements [10 CFR 50.55a Request VR-1, Revision 0] in a safety evaluation dated October 22, 2009.
 
===4. Reason for Request===
On May 19, 2011, the NRC issued Amendments 156 and 157 that modified the scram time testing frequency requirements of Technical Specifications (TS) 3.1.4, "Control Rod Scram Times." Approval of this proposed alternative to ISTC-3510 would align the testing frequencies of the specified ASME code components to the frequencies stated within TS Surveillance Requirement (SR) 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3 and SR 3.1.4.4.
The pneumatically operated scram inlet and exhaust valves are not provided with suitable position indication; therefore, to measure stroke times as required by ISTC-5131(a), special test methods or test equipment would be required.
The check valves are not provided with position indication; therefore, to determine if the obturator has traveled to the proper position as required by ISTC-5221(a),
special test methods or test equipment would be required.
Approval of this proposed alternative would make the third 10-year inservice test program consistent with NUREG-1482, Revision 1, Section 4.4.6.
 
Page 3 of 4
: 5. Proposed Alternative and Basis for Use As discussed in NUREG-1482, Revision 1, Section 4.4.6, the rod scram test frequency identified in the facility's Technical Specifications may be used as the valve testing frequency to minimize rapid reactivity transients and wear of the control rod drive mechanisms. The scram inlet and exhaust valves are pneumatically operated valves that full-stroke in milliseconds and are not provided with suitable position indication. The check valves are not equipped with position indication.
Verifying that the associated control rod meets the scram insertion time limits defined in the plant's Technical Specifications can be an acceptable alternative method of detecting degradation of these valves.
The provisions of this request provide a reasonable alternative to the ISTC-3510, ISTC-5131(a) and ISTC-5221(a) code requirements. The proposed method of detecting valve degradation provides reasonable assurance of each valve's operational readiness, provides an acceptable level of quality and safety for monitoring the valves, and ensures the valves are capable of performing their control rod drive safety functions.
The Technical Specification 3.1.4 surveillances place conservative limits on the control rod insertion times, ensuring the necessary quality of the control rod drive system and its components are maintained. Therefore, scram insertion timing per the requirements of SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3 and SR 3.1.4.4, including their test frequencies, shall be substituted for individual valve testing. For check valves 1C11-114 and 1C11-115, this includes only OPEN direction testing.
: 6. Duration of Proposed Alternative The proposed alternative shall be utilized during the third 10-year inspection interval currently scheduled to expire on May 17, 2019.
: 7. Precedent Safety Evaluation of the Inservice Testing Program Second Ten-Year Interval for Pumps and Valves - Perry Nuclear Power Plant (TAC No. MA3328),
August 9, 1999.
Perry Nuclear Power Plant - Safety Evaluation of Relief Requests for Third 10-year Pump and Valve Inservice Testing Program (TAC Nos. ME0191 Through ME0198),
October 22, 2009.
Cooper Nuclear Station - Request for Relief No. RV-06 for the Fourth 10-Year Interval Inservice Testing Program Regarding Control Rod Drive System Valves (TAC NO..ME1521), April 26, 2010.
 
Page 4 of 4
: 8. References
: 1. Perry Nuclear Power Plant, Technical Specification 3.1.4, "Control Rod Scram Times."
: 2. NUREG-1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants," U.S. Nuclear Regulatory Commission.
: 3. Perry Nuclear Power Plant, Refueling Outage Justification RO-31, Control Rod Drive Hydraulic System (C11), Valve 1C11-115.
: 4. U.S. Nuclear Regulatory Commission letter to FENOC,
 
==Subject:==
Perry Nuclear Power Plant, Unit No. 1 - Issuance of Amendment re: License Amendment to Revise Technical Specification (TS) 3.1.4, "Control Rod Scram Times," to Incorporate Technical Specification Task Force (TSTF) Change Traveler TSTF-460, Revision 0 (TAC No. ME5194), May 19, 2011.
[Amendment 156]
: 5. U.S. Nuclear Regulatory Commission letter to FENOC,
 
==Subject:==
Perry Nuclear Power Plant, Unit No. 1 - Issuance of Amendment re: License Amendment to Modify Technical Specification (TS) 3.1.4, "Control Rod Scram Times," to Incorporate Technical Specification Task Force (TSTF) Change Traveler TSTF-222, Revision 0 (TAC No. ME5192), May 19, 2011.
[Amendment 157]}}

Latest revision as of 14:23, 12 November 2019

10 CFR 50.55a Request VR-1, Revision 1, Align Valve Testing Frequencies to NUREG-1482 Provision
ML112900204
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 10/16/2011
From: Bezilla M
FirstEnergy Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
References
L-11-287, NUREG-1482
Download: ML112900204 (5)
v • d • e


Text

FENOC Perry Nuclear Power Plant 10 Center Road FirstEnergy Nuclear Operating Company Perry, Ohio 44081 MarkB.Bezilla 440-280-5382 Vice President Fax: 440-280-8029 October 16, 2011 L-11-287 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440, License No. NPF-58 10 CFR 50.55a Request VR-1. Revision 1. Align Valve Testing Frequencies to NUREG-1482 Provision By correspondence dated May 19, 2011 (Accession No. ML111050267), the Nuclear Regulatory Commission (NRC) issued Amendment 156 to Facility Operating License No. NPF-58 for the Perry Nuclear Power Plant (PNPP). The amendment modified the frequency of Surveillance Requirement (SR) 3.1.4.2 from "120 days cumulative operation in MODE 1" to "200 days cumulative operation in MODE 1."

Pursuant to 10 CFR 50.55a(a)(3), FirstEnergy Nuclear Operating Company (FENOC) is requesting NRC approval for a proposed alternative to certain requirements of the PNPP Inservice Testing Program (ISTP). Approval of the enclosed alternative would align the valve testing to the test frequencies in Technical Specification 3.1.4, "Control Rod Scram Times," making the ISTP consistent with NUREG-1482, "Guidelines for Inservice Testing at Nuclear Power Plants."

FENOC is requesting approval of the proposed alternative by March 2, 2012. The proposed alternative would be implemented prior to the March 10, 2012 scheduled date to perform SR 3.1.4.2 for control rod scram time testing.

There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil Lashley, Supervisor - Fleet Licensing, at (330) 315-6808.

Sincerely, Mark B. Bezilla

Enclosure:

Perry Nuclear Power Plant, 10 CFR 50.55a Request VR-1, Revision 1 cc: NRC Region III Administrator NRC Resident Inspector

' NRC Project Manager

Perry Nuclear Power Plant 10 CFR 50.55a Request VR-1, Revision 1 Page 1 of 4 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)

-Alternative Provides Acceptable Level of Quality and Safety-

1. ASME Code Componentfs) Affected Category B Valves (Typical of 177) 1C11-126, Scram Inlet Valve (Class 2) 1C11-127, Scram Exhaust Valve (Class 2)

Category C Valves (Typical of 177) 1C11-114, Scram Discharge Header Check Valve (Class 2)

[OPEN direction only]

1C11-115, Charging Water Header Check Valve (Class 2)

[OPEN direction only]

These valves operate as an integral part of their respective hydraulic control unit (typical of 177) to rapidly insert the control rods into the core in support of the reactor scram function. Specifically:

Scram Inlet Valve (1C11-126) has a safety function to open and supply pressurized water to the bottom of the control rod drive piston to rapidly insert the control rod into the core.

Scram Exhaust Valve (1C11-127) has a safety function to open and vent water from above the control rod drive piston to the scram discharge header allowing control rod movement during the scram.

Scram Discharge Header Check Valve (1C11-114) has a safety function to close and prevent reverse flow from the scram discharge header back to the top of the control rod drive piston; during the scram, this check valve has a safety function to open and allow water from above the control rod drive piston to flow into the scram discharge header (with 1C11-127 open) allowing control rod movement.

Charging Water Header Check Valve (1C11-115) has a safety function to close and prevent the loss of water pressure in the event supply pressure to the scram accumulator is lost; during the scram, this check valve opens to allow flow to the bottom of the control rod drive piston (with 1C11-126 open).

Page 2 of 4

2. Applicable Code Edition and Addenda

American Society of Mechanical Engineers (ASME) OM Code-2001 Edition, Code for Operation and Maintenance of Nuclear Plants, with Addenda through OMb-2003.

3. Applicable Code Requirements ISTC-3510, Exercising Test Frequency states, "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520..."

ISTC-5131(a), Valve Stroke Testing states, "Active valves shall have their stroke times measured when exercised in accordance with ISTC-3500."

ISTC-5221(a), Valve Obturator Movement states, "The necessary valve obturator movement during exercising shall be demonstrated by performing both an open and a close test."

The Nuclear Regulatory Commission (NRC) approved an alternative to these requirements [10 CFR 50.55a Request VR-1, Revision 0] in a safety evaluation dated October 22, 2009.

4. Reason for Request

On May 19, 2011, the NRC issued Amendments 156 and 157 that modified the scram time testing frequency requirements of Technical Specifications (TS) 3.1.4, "Control Rod Scram Times." Approval of this proposed alternative to ISTC-3510 would align the testing frequencies of the specified ASME code components to the frequencies stated within TS Surveillance Requirement (SR) 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3 and SR 3.1.4.4.

The pneumatically operated scram inlet and exhaust valves are not provided with suitable position indication; therefore, to measure stroke times as required by ISTC-5131(a), special test methods or test equipment would be required.

The check valves are not provided with position indication; therefore, to determine if the obturator has traveled to the proper position as required by ISTC-5221(a),

special test methods or test equipment would be required.

Approval of this proposed alternative would make the third 10-year inservice test program consistent with NUREG-1482, Revision 1, Section 4.4.6.

Page 3 of 4

5. Proposed Alternative and Basis for Use As discussed in NUREG-1482, Revision 1, Section 4.4.6, the rod scram test frequency identified in the facility's Technical Specifications may be used as the valve testing frequency to minimize rapid reactivity transients and wear of the control rod drive mechanisms. The scram inlet and exhaust valves are pneumatically operated valves that full-stroke in milliseconds and are not provided with suitable position indication. The check valves are not equipped with position indication.

Verifying that the associated control rod meets the scram insertion time limits defined in the plant's Technical Specifications can be an acceptable alternative method of detecting degradation of these valves.

The provisions of this request provide a reasonable alternative to the ISTC-3510, ISTC-5131(a) and ISTC-5221(a) code requirements. The proposed method of detecting valve degradation provides reasonable assurance of each valve's operational readiness, provides an acceptable level of quality and safety for monitoring the valves, and ensures the valves are capable of performing their control rod drive safety functions.

The Technical Specification 3.1.4 surveillances place conservative limits on the control rod insertion times, ensuring the necessary quality of the control rod drive system and its components are maintained. Therefore, scram insertion timing per the requirements of SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3 and SR 3.1.4.4, including their test frequencies, shall be substituted for individual valve testing. For check valves 1C11-114 and 1C11-115, this includes only OPEN direction testing.

6. Duration of Proposed Alternative The proposed alternative shall be utilized during the third 10-year inspection interval currently scheduled to expire on May 17, 2019.
7. Precedent Safety Evaluation of the Inservice Testing Program Second Ten-Year Interval for Pumps and Valves - Perry Nuclear Power Plant (TAC No. MA3328),

August 9, 1999.

Perry Nuclear Power Plant - Safety Evaluation of Relief Requests for Third 10-year Pump and Valve Inservice Testing Program (TAC Nos. ME0191 Through ME0198),

October 22, 2009.

Cooper Nuclear Station - Request for Relief No. RV-06 for the Fourth 10-Year Interval Inservice Testing Program Regarding Control Rod Drive System Valves (TAC NO..ME1521), April 26, 2010.

Page 4 of 4

8. References
1. Perry Nuclear Power Plant, Technical Specification 3.1.4, "Control Rod Scram Times."
2. NUREG-1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants," U.S. Nuclear Regulatory Commission.
3. Perry Nuclear Power Plant, Refueling Outage Justification RO-31, Control Rod Drive Hydraulic System (C11), Valve 1C11-115.
4. U.S. Nuclear Regulatory Commission letter to FENOC,

Subject:

Perry Nuclear Power Plant, Unit No. 1 - Issuance of Amendment re: License Amendment to Revise Technical Specification (TS) 3.1.4, "Control Rod Scram Times," to Incorporate Technical Specification Task Force (TSTF) Change Traveler TSTF-460, Revision 0 (TAC No. ME5194), May 19, 2011.

[Amendment 156]

5. U.S. Nuclear Regulatory Commission letter to FENOC,

Subject:

Perry Nuclear Power Plant, Unit No. 1 - Issuance of Amendment re: License Amendment to Modify Technical Specification (TS) 3.1.4, "Control Rod Scram Times," to Incorporate Technical Specification Task Force (TSTF) Change Traveler TSTF-222, Revision 0 (TAC No. ME5192), May 19, 2011.

[Amendment 157]

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