ML14223A581

Monticello Nuclear Generating Plant - Alternative Request Vr 05 to the Testing Requirements of the ASME OM Code for the Fifth 10-Year Inservice Inspection Program Interval (TAC No. MF4544)

ML14223A581
Person / Time
Site:	Monticello
Issue date:	08/27/2014
From:	David Pelton Plant Licensing Branch III
To:	Fili K D Northern States Power Co, Xcel Energy
Beltz T A
References
TAC MF4544
Download: ML14223A581 (9)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 27, 2014 Karen D. Fili Site Vice-President Northern States Power Company -Minnesota Monticello Nuclear Generating Plant 2807 West County Road 75 Monticello, MN 55362-9637

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT -ALTERNATIVE TO THE TESTING REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS CODE FOR OPERATIONS AND MAINTENANCE OF NUCLEAR POWER PLANTS FOR THE FIFTH 10-YEAR INSERVICE INSPECTION PROGRAM INTERVAL (TAG NO. MF4544)

Dear Mrs. Fili:

By letter dated July 30, 2014, Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for authorization of an alternative to the testing requirements of the American Society of Mechanical Engineers (ASME) Code for Operations and Maintenance of Nuclear Power Plants (OM Code), 2004 Edition with Addenda through OMb Code-2006, for the Monticello Nuclear Generating Plant (MNGP). Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.55a(g)(3)(ii), the licensee requested to defer its quarterly valve exercise testing on the inboard and outboard main steam line drain valves (M0-2373 and M0-2374) to the next MNGP refueling outage in spring 2015 on the basis that complying with the specified requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff has reviewed MNGP Request No. VR 05 and concludes, as set forth in the enclosed safety evaluation, that NSPM has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55(a)3)(ii) and remains in compliance with ASME OM Code requirements. Therefore, the NRC staff authorizes the proposed alternative request VR 05 for the fifth 1 0-year inservice testing interval at MNGP which began on September 1, 2012, and is currently scheduled to end on August 31, 2022. The proposed alternative shall only be utilized until completion of the MNGP spring 2015 refueling outage.

K. Fili If you have any questions, please contact Terry Beltz at (30 1) 415-3049 or via e-mail at Terry. Beltz@nrc.gov. Docket No. 50-263

Enclosure:

Sincerely, Dav1d L. Pelton, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Staff Evaluation of the Fifth 1 0-Year lnservice Inspection Interval Alternative Request No. VR 05 cc w/encl: Distribution via ListServ REG(/{ UNITED STATES NUCLEAR REGULATORY COMMISSION ! WASHINGTON, D.C. 20555-0001 <( 0 \n r;; '('/. 1--? -.,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE FIFTH 10-YEAR INSERVICE INSPECTION PROGRAM INTERVAL REQUEST NO. VR 05 MONTICELLO NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY-MINNESOTA DOCKET NO. 50-263

1.0 INTRODUCTION

By letter to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated July 30, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML 14212A071), Northern States Power Company (NSPM, the licensee). doing business as Xcel Energy, submitted alternative request VR 05 for the Monticello Nuclear Generating Plant (MNGP). The licensee requested an alternative test plan in lieu of certain inservice testing (1ST) requirements of the 2004 Edition with 2006 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the 1ST program at MNGP during the fifth 1 0-year 1ST program interval, which began on September 1, 2012, and is currently scheduled to conclude on August 31, 2022. Specifically, NSPM requested to defer its quarterly valve exercise testing on the inboard and outboard main steam line drain valves (M0-2373 and M0-237 4, respectively) to the next refueling outage in spring 2015 at MNGP. Pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) Section 50.55a(a)(3)(ii), the licensee requested the use of proposed alternative VR 05 since complying with the current ASME OM Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff's evaluation of the licensee's proposed alternative request is provided below.

2.0 REGULATORY EVALUATION

The regulations under 10 CFR 50.55a(f), "lnservice Testing Requirements," require, in part, that 1ST of certain ASME Code Class 1, 2, and 3 components must meet the requirements of the ASME OM Code and applicable addenda, except where alternatives have been authorized pursuant to paragraphs (a)(3)(i) or (a)(3)(ii). Pursuant to 10 CFR 50.55a(f)(6)(i), a licensee may submit a request for relief from the given requirements, along with information to support the determination. The Commission is authorized to Enclosure evaluate a licensee's relief request, and may grant the requested relief or impose alternative requirements, considering the burden that the licensee might incur if the Code requirements were enforced for the given facility. Pursuant to 10 CFR 50.55a(a)(3)(i) and 10 CFR 50.55a(a)(3)(ii), the Commission may also authorize the licensee to implement an alternative to the Code requirements, provided that the alternative either provides an acceptable level of quality and safety, or compliance with the Code requirement would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Based on the above, and pursuant to the NRC staff's findings with respect to authorizing the alternative VR 05 as given below, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the relief requested by the licensee. MNGP is currently in its fifth 1 0-year 1ST program interval. The fifth 1 0-year 1ST program interval began on September 1, 2012, and is currently scheduled to conclude on August 31, 2022. Finally, NSPM states in the submittal its commitment to the ASME OM Code, 2004 Edition, with Addenda through OMb Code-2006.

3.0 TECHNICAL EVALUATION

3.1 Licensee's Alternative Request VR 05 ASME OM Code Requirement ISTC-3510, "Exercising Test Frequency", states, in part, that "Active Category A, Category 8, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3570, ISTC-5221, and ISTC-5222." Alternative testing is requested for the following valves: Table 1 Valve 10 System Category Class M0-2373 Main Steam Line Drain Valve-Inboard A 1 M0-2374 Main Steam Line Drain Valve -Outboard A 1 Reason for Request In its July 30, 2014, submittal, the licensee provided the following reasons to support its request: In May 2014, an upward trend in unidentified drywellleakage was identified in conjunction with an increased radiation count rate on the drywell continuous air monitor. These changes occurred during exercise (stroke time) testing of M0-2373. The licensee suspected that the increase in unidentified drywell leakage to be the result of a possible packing leak on M0-2373, and that backseating the valve could likely reduce leakage into the drywell. The licensee developed a backseat testing methodology to maintain the functional performance parameters of both the inboard and outboard valves within acceptable limits. On July 10, 2014, M0-2373 was backseated and testing performed to demonstrate operability of the valves. After completion of the testing on M0-2373, it was fully-opened and backseated to isolate the packing leak. The unidentified leakage in the drywell was reduced to the level that existed prior to exercising M0-2373. With M0-2373 on its backseat, M0-237 4 was closed and de-energized to prevent opening due to 10 CFR 50, Appendix R concerns. The next quarterly valve exercise testing of M0-2373 and M0-2374 is on October 10, 2014. The licensee is requesting to defer this quarterly testing until the next MNGP refueling outage, scheduled for the spring of 2015. Performance of the quarterly exercise testing would require multiple opening and closing evolution of the both valves, including the need to re-energize and de-energize the circuit breaker for M0-237 4. Multiple opening and closing of M0-2373 has the potential to increase drywell leakage, which the backseating operation has previously restored to normal levels. As previously discussed, quarterly exercise testing of both valves with M0-2373 on its backseat requires multiple circuit breaker manipulations. The quarterly test starts with M0-2373 being stroke timed closed. Next, the circuit breaker for M0-2374 would have to be closed to restore power to M0-2374. M0-2374 would be stroke timed open and closed, and then the circuit breaker for M0-237 4 would be reopened. M0-2373 would then be stroke-timed open and placed on its backseat to reduce unidentified drywell leakage resulting from the packing leak. This evolution would be required to be performed each quarter (two more quarterly tests) until the refueling outage in the spring of 2015 when the valve will be repaired. The repeated backseating of M0-2373 increases the risk of causing damage to the backseat or valve stem as described in NRC Information Notice 87-40, "Backseating Valves Routinely to Prevent Packing Leakage." Each time that a valve is placed on its backseat requires opening the circuit breaker and connecting a reduced voltage source to the motor-operated valve bypassing the open circuit until the motor is stalled. The reduced voltage source is then removed and the circuit breaker is closed. Repeatedly performing this evolution increases the potential for human errors to occur. Motor damage could also occur if the locked-rotor current is in excess of 15 seconds. If reduced voltage is not properly controlled during the evolution, then the valve backseat or stem may be damaged. Finally, an increase in unidentified drywell leakage, such as might occur from repeated cycling of M0-2373, could ultimately result in a Technical Specification required shutdown. In NUREG 1482, "Guidelines for lnservice Testing at Nuclear Power Plants: lnservice Testing of Pumps and Valves and lnservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants-Final Report," Revision 2, Section 3.1.1, it states that a licensee may request relief from quarterly testing where such testing would impose a hardship, such as entering a limiting condition for operations of 3 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in duration or repositioning a circuit breaker from "off' to "on." Other acceptable reasons for relief include the need to keep personnel radiation exposure as low as reasonably achievable (ALARA), and personnel safety. Repair of M0-2373 valve packing would require entry into the drywell (i.e., primary containme.nt). Entry into the drywell requires the plant to either enter Mode 3 (Hot Shutdown) or reduce reactor power below 10 percent to minimize radiation levels. Personnel entry into the drywell with the plant at operation is increases risk due to radiation exposure and does not support the practice of maintaining ALARA. Drywell entry presents a personnel safety concern due to high ambient temperatures, and it is typically inaccessible during normal power operation due to being inerted with nitrogen gas. Additionally, maneuvering the reactor to below 10 percent power or into Mode 3 involves an inherent risk and increases the nuclear safety risks due to cycling plant equipment. The licensee states that maintaining the packing leak isolated with the M0-2373 backseated in the open position and M0-2374 closed is the lower risk option. For all of these reasons, NSPM states that with the current plant configuration the quarterly exercise testing of M0-2373 and M0-237 4 involves a hardship. There is not a sufficient corresponding increase in the level of safety versus the potential to increase drywell unidentified leakage or cause further damage to M0-2373. Proposed Alternative The main steam line drain valves are exercise tested quarterly: The present configuration of having M0-2373 backseated in the open position to decrease drywell leakage, and closing and de-energizing M0-2374 to isolate the containment penetration, is a temporary configuration. Quarterly exercise testing of the M0-2373 from the backseated position increases vulnerability of having unacceptable drywell leakage, for which the backseating operation was previously performed and which reduced drywell leakage to acceptable levels. NSPM proposes to stroke M0-2373 and M0-2374 during the next MNGP refueling outage in lieu of the current quarterly exercise testing. Both valves have successfully passed each quarterly exercise test since plant startup from the 2013 refueling outage. Historical exercise trending results for both valves for performances prior to the 2013 refueling outage are consistent with current cycle results. Both M0-2373 and M0-237 4 are normally closed during power operation. The valves safety function is to close to prevent inventory loss following a main steam line pipe break outside containment and to provide containment isolation. The proposed operating configuration for the remainder of the cycle maintains the required safety function of containment isolation. Multiple backseating evolutions of M0-2373 could potentially result in either backseat or stem damage, and quarterly exercise testing unnecessarily challenges this safety function. Also, since both valves are normally closed during power operation, there are no operational reasons to require stroking of these valves during this period. NSPM requests to extend the exercise testing due to the hardship without a compensating increase in the level of quality and safety presented by the temporary configuration of the main steam line drain valves. There is reasonable assurance that these valves will perform their safety function to close to prevent inventory loss following main steam line pipe breaks outside containment and to provide containment isolation. The proposed alternative identified in this relief request shall be utilized until the next MNGP refueling outage in spring of 2015. 3.2 NRC Staff Evaluation ASME OM Code requirement ISTC-3510 requires that active Category A and B valves be exercised nominally every three months. In addition, the ASME OM Code specifies that if the exercise tests are not practicable to perform during power operation, the test may be deferred to either cold shutdowns or refueling outages. The licensee has been exercise testing the valves noted in Table 1 nominally every three months. However, following the exercise testing completed in May 2014, there was a noted increase in drywall unidentified leakage due to possible valve packing leakage from M0-2373. Continued operation of M0-2373 in its normally closed position could mask or potentially challenge the technical specification acceptance criteria for reactor coolant system operational leakage associated with unidentified leakage. Repair of the valve packing would require the plant either reduce reactor power or enter Mode 3. To preclude a potential plant power reduction or shutdown, the licensee electrically backseated M0-2373 to seal off the packing area, operationally tested it from this configuration, and then opened it on the backseat. Unidentified leakage in the drywall returned to expected levels, thus supporting the most likely source of the increased leakage to be from M0-2373 packing. Continuation with quarterly exercise testing and maintaining a normally closed valve position could result in an unnecessary plant shutdown which is considered an impractical condition as noted in NUREG-1482 Revision 2, Section 2.4.5. Continuation with the quarterly valve exercise testing and returning the faulty valve to a backseated configuration requires several special valve stroke manipulations at the motor control center. This represents an additional hardship or unusual difficulty without a compensating increase in the level of quality or safety. The licensee proposes to maintain the current configuration of maintaining M0-2374 in the closed (i.e., safety) position with the valve motor electrically de-energized, and with M0-2373 in the full-open and backseated position with electrical power provided to maintain isolation capability on receipt of an automatic close signal. This configuration will be maintained until maintenance can be performed at the next refueling outage, currently scheduled for the spring of 2015. The NRC staff finds that the proposed alternative is within the ASME OM Code guidelines for deferring impractical exercise testing to the refueling outage and provides reasonable assurance that the components remain operationally ready.

4.0 CONCLUSION

As set forth above, the NRC staff determines that the proposed alternative described in alternative request VR 05 provides reasonable assurance that valves listed in Table 1 are operationally ready. Accordingly, the staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii), and is in compliance with the ASME OM Code requirements. Therefore, the NRC staff authorizes the proposed alternative in request VR 05 at MNGP for the fifth 1ST interval which began on September 1, 2012, and is currently scheduled to end on August 31, 2022. The proposed alternative is only authorized until completion of the MNGP spring 2015 refueling outage. All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable. Principle Contributor: Michael Farnan, NRR Date of issuance: August 2 7, 2014 K. Fili If you have any questions, please contact Terry Beltz at (301) 415-3049 or via e-mail at Terry.Beltz@nrc.gov. Docket No. 50-263

Enclosure:

Sincerely, IRA/ David L. Pelton, Chief Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Staff Evaluation of the Fifth 10-Year lnservice Inspection Interval Alternative Request No. VR 05 cc w/encl: Distribution via ListServ DISTRIBUTION: PUBLIC RidsNrrDorllpl3-1 Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrPMMonticeilo Resource RidsNrrLAMHenderson Resource LPL3-1 R/F RidsNrrDeEpnb Resource RidsNrrDoriDpr Resource RidsRgn3Mai1Center Resource TBowers, EDO R-Ill DAiley, NRR MFarnan, NRR ADAMS A ccesston N ML 14223A 81 o.: 5

• 0 *1 d d A v1a e-ma1 ate 0 ugust7,2 14 OFFICE LPL3-1/PM LPL3-1/LA EPNB/BC LPL3-1/BC NAME TBeltz MHenderson DAiley* DPelton DATE 08/14/2014 08/13/2014 08/07/2014 08/27/2014 OFFICIAL RECORD COPY