View source for CP-201500671, Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3.

{{Adams
| number = ML15198A150
| issue date = 06/30/2015
| title = Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3.
| author name = Flores R, Mccool T
| author affiliation = Luminant Generation Co, LLC, Luminant Power
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000445, 05000446
| license number = 
| contact person = 
| case reference number = CP-201500671, TXX-15102
| document type = Code Relief or Alternative, Inservice/Preservice Inspection and Test Report, Letter type:CP
| page count = 6
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:Senior Vice President               P0O Box 1002 Rafael Flores                       Luminant Power
                                                         & Chief Nuclear Officer             6322 North FM 56 Luminant                                                 Rafael.Flores@Luminant.com
                                                                                                        ,o Glen Rose, TX 76043 C 817 5590O403 F 254 897 6652 CP-201500671                                                                      Ref. # 10CFR50.55a(z)(2)
TXX-15102 June 30, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

==SUBJECT:==
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NOS. 50-445 AND 50-446 RELIEF REQUEST T-1 FOR UNMTS 1 AND 2 INSERVICE TESTING PROGRAM FOR APPLICATION OF AN ALTERNATIVE TO THE ASME OM CODE FREQUENCY SPECIFICATIONS (2007 EDITION OF ASME CODE, SECTION XI, 2008 ADDENDA THIRD INTERVAL START DATE: AUGUST 3, 2013 THIRD INTERVAL END DATE: AUGUST 2, 2023)

==Dear Sir or Madam:==

Pursuant to 10 CFR 50.55a(z)(2), Luminant Generation Company, LLC (Luminant Power) is submitting Relief Request T-1 (see attachment) for Comanche Peak Units 1 and 2 for the third ten year inservice testing interval. Luminant Power is requesting an alternative for the frequency specifications as specified in Code Case OMN-20. Compliance with the frequency specifications of the ASME OM Code would result in a hardship without a compensating increase in the level of quality and safety.
Luminant Power requests approval of this relief request by March 31, 2016, to support the upcoming CPNPP Unit 1 refueling outage.
This communication contains no new licensing basis commitments regarding Comanche Peak Units 1 and 2. Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.
Sincerely, Luminant Generation Company LLC Rafael Flores By:_
Tom P. McCool Vice President, Nuclear Engineering & Support

U. S. Nuclear Regulatory Commission TXX-15 102 Page 2 of 2 06/30/201 5 Attachment       -  Relief Request T-1 Code Case OMN-20 Inservice Test Frequency c -         Marc L. Dapas, Region IV Baiwant K. Singal, NIR Resident Inspectors, Comanche Peak Robert Free, TDLR Jack Ballard, ANII, Comanche Peak

Attachment to TXX-15102 Page 1 of 4 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 & 2 Relief Request Number T-1 Code Case OMN-20 Inservice Test Frequency (Third 10-Year IST Interval Start Date: August 3, 2013)
: 1. ASME Code Component Affected:
All pumps and valves contained within the Inservice Testing (IST) Program
: 2. Applicable Code Edition and Addenda:
American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (i.e., GM Code), 2004 Edition through 2006 Addenda (Reference 1)
: 3. Applicable Code Requirement:
This request applies to the frequency specifications of the ASME GM Code paragraphs as identified below. The frequencies for tests given in the ASME GM Code do not include a tolerance band.
Test Type                           Test Frequency (nominal)              Code Reference Pump Test                           3 months                              GM ISTB Valve Position Indication           2 years                               GM ISTC Verification Valve Exercising Test               3 months                              GM ISTC Valve Fail-Safe Test                3 months                              GM ISTC Valve Leak Rate Test                2 years                               GM ISTC (Non-Containment Isolation Valves)
Frequency per Appendix I              10CFR50 App. J (Containment Isolation Valves)
Check Valve Exercise Test           3 months                              GM ISTC Safety/Relief Valve Setpoint        5 years                               GM Appendix I Test                                (class 1, class 2 MSSV) 10 years                              GM Appendix I (class 2, 3)
: 4. Reason for Request: Undue hardship without a compensatin* increase inthe level of          qualitjy and safety (10CFR50.55a(z)(2)).
Pursuant to 10 CFR 50.55a, "Codes and standards," paragraph (z)(2), an alternative is being requested from the frequency specifications of the ASME GM Code for Comanche Peak Nuclear Power Plant, Units 1 and 2. The basis of the alternative request is that the Code frequency specifications present an undue hardship without a compensating increase in the level of quality and safety.
ASME GM Code Section 1ST establishes the inservice test frequency for all components within the scope of the Code. The frequencies (e.g., quarterly) have historically been interpreted as "nominal" frequencies (generally as defined in the Table 3.2 of NUREG-1482, Guidelines for lnservice Testing at Nuclear Power Plants, Revision 2 (Reference 2)) and owners routinely applied the surveillance

Attachment to TXX-15102 Page 2 of 4 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 & 2 Relief Request Number T-1 Code Case OMN-20 Inservice Test Frequency (Third 10-Year IST Interval Start Date: August 3, 2013) extension time period (i.e., grace period) contained in the plant Technical Specifications (TSs)
Surveillance Requirements (SRs). The TSs typically allow for a less than or equal to 25% extension of the surveillance test interval to accommodate plant conditions that may not be suitable for conducting the surveillance (TS SR 3.0.2). However, Regulatory Issue Summary 2012-10, NRC Staff Position on Applying Surveillance Requirements (SRs) 3.0.2 and 3.0.3 to Administrative Controls Program Tests (Reference 3), states that SR 3.0.2 and 3.0.3 cannot be applied to TS 5.5, Programs and Manuals, for tests that are not associated with a TS SR. TS SR 3.0.2 is equivalent to SR 3.0.2 contained in NUREG-1431, Standard Technical Specifications, Westinghouse Plants (Reference 4).
The lack of a tolerance band on the ASME GM Code 1ST frequency restricts operational flexibility.
There may be a conflict where a surveillance test could be required (iLe., its frequency could expire),
but where it is not possible or not desired that it be performed until sometime after a plant condition or associated Limiting Condition for Operation (LCO) is within its applicability.
The NRC recognized this potential issue in the TSs by allowing a frequency tolerance as described in TS SR 3.0.2. The lack of a similar tolerance applied to GM Code testing places an unusual hardship on the plant to adequately schedule work tasks without operational flexibility. Thus, just as with TS-required surveillance testing, some tolerance is needed to allow adjusting GM Code testing intervals to suit the plant conditions and other maintenance and testing activities. This assures operational flexibility when scheduling surveillance tests and minimizes conflict between the need to complete the surveillance and plant conditions.
: 5. Proposed Alternative and Basis for Use:
10CFR50.55a(z) states:
            "Alternatives to the requirements of paragraphs (b) through (h) of this section or portions thereof may be used when authorized by the Director, Office of Nuclear Reactor Regulation, or Director, Office of New Reactors, as appropriate. A proposed alternative must be submitted and authorized prior to implementation. The applicant or licensee must demonstrate that:
(1)      The proposed alternative would provide an acceptable 'level of quality and safety; or (2)      Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
Luminant believes that the compliance with the Code frequency specifications presents an undue hardship without a compensating increase in the level of quality and safety.
Code Case OMN-20 is included in the ASME GM Code, 2009 Edition, and is proposed for use as an alternative in determining acceptable tolerances for pump and valve test frequencies of the ASME GM Code. This code case was approved by the ASME GM Code Standards Committee in February 2012.
The requirements of Code Case OMN-20 are described below.
ASME GM, Division 1, Section IST and earlier editions and addenda of ASME GM Code specify component test frequencies based either on elapsed time periods (e.g., quarterly, 2 years) or on the occurrence of plant conditions or events (e.g., cold shutdown, refueling outage, upon detection of a sample failure, following maintenance) as discussed below.

Attachment to TXX-15102 Page 3 of 4 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 & 2 Relief Request Number T-1 Code Case OMN-20 Inservice Test Frequency (Third 10-Year IST Interval Start Date: August 3, 2013) a)     Components whose test frequencies are based on elapsed time periods shall be tested at the frequencies specified in Section 1ST with a specified time period between tests as shown in the table below. The specified time period between tests may be reduced or extended as follows:
: 1)  For periods specified as less than 2 years, the period may be extended by up to 25% for any given test.
: 2)  For periods specified as greater than or equal to 2 years, the period may be extended by up to 6 months for any given test.
: 3)  All periods specified may be reduced at the discretion of the owner (i.e., there is no minimum period requirement).
Period extension is to facilitate test scheduling and considers plant operating conditions that may not be suitable for performance of the required testing (e.g., performance of the test would cause an unacceptable increase in the plant risk profile due to transient conditions or other ongoing surveillance, test or maintenance activities). Period extensions are not intended to be used as a routine action for mere operational convenience.
Period extensions may also "be applied to accelerated test frequencies (e.g., pumps in Alert Range) and other less than two year test frequencies not specified in the table below.
Period extensions may not be applied to the test frequency requirements specified in Subsection ISTD, Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants, as Subsection ISTD contains its own rules for period extensions.
Frequency                    [I      Specified Time Period Between Tests       ]
Quarterly (or every 3 months)                                             92 days Semiannually (or every 6 months)                                         184 days Annually (or every year)                                                 366 days x Years                                             x calendar years where 'x' is a whole number of
________________________________years >      2 b)     Components whose test frequencies are based on the occurrence of plant conditions or events may not have their period between tests extended except as allowed by ASME OM, Division: 1, Section 1ST, 2009 Edition through OMa-2011 Addenda and earlier editions and addenda.
: 6. Duration of Proposed Alternative:
This proposed alternative will be utilized for the remainder of the CPNPP, Units 1 and 2, third 10-year 1ST interval, which began on August 3, 2013 and will end on August 3, 2023.
: 7. Precedents:
The proposed alternative request for CPNPP is similar to the following approved alternative/relief requests shown below:

Attachment to TXX-1 5102 Page 4 of 4 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 & 2 Relief Request Number T-1 Code Case OMN-20 Inservice Test Frequency (Third 10-Year IST Interval Start Date: August 3, 2013)
: 1) Alternative Request RV-01 was approved by the NRC for Quad Cities Units 1 and 2 on February 14, 2013 (ADAMS Accession No. ML13042A348).
: 2)     Alternative Request RR-4-01 was approved by the NRC for Virgil C. Summer Unit 1 on November 5, 2013 (ADAMS Accession No. ML13301A767).
: 3)     Alternative Request C-i was approved by the NRC for Surry Units 1 and 2 on April 23, 2014 (ADAMS Accession No. ML14111A241).
: 4)     Alternative Request G-001 was approved by the NRC for Millstone Units 2 and 3 on July 10, 2014 (ADAMS Accession No. ML14163A586).
: 8.   

==Reference:==
: 1) ASME CM Code, 2004 Edition, Addenda through 2006
: 2)     NUREG-1482, Revision 2, Guidelines for lnservice Testing at Nuclear Power Plants
: 3)      Regulatory Issue Summary 2012-10, NRC Staff Position on Applying Surveillance Requirements 3.0.2 and 3.0.3 to Administrative Controls Program Tests
: 4)     NUJREG-1431, Revision 4, Standard Technical Specifications, Westinghouse Plants.}}