ML12172A037
| ML12172A037 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/26/2012 |
| From: | Lynnea Wilkins Plant Licensing Branch IV |
| To: | O'Grady B Nebraska Public Power District (NPPD) |
| Wilkins L | |
| References | |
| TAC ME6420, BL-11-001 | |
| Download: ML12172A037 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 26, 2012 Mr. Brian J. O'Grady Vice President-Nuclear and CNO Nebraska Public Power District 72676 648A Avenue Brownville, NE 68321
SUBJECT:
COOPER NUCLEAR STATION - CLOSEOUT OF NRC BULLETIN 2011-01, "MITIGATING STRATEGIES" (TAC NO. ME6420)
Dear Mr. O'Grady:
On May 11, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating Strategies" (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML111250360). to all holders of operating licenses for nuclear power reactors.
except those that have permanently ceased operation and have certified that fuel has been removed from the reactor vessel. The purpose of the bulletin was to obtain a comprehensive verification that licensees' mitigating strategies to maintain or restore core cooling. spent fuel cooling. and containment following a large explosion or fire were compliant with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.54(hh)(2).
The bulletin required two sets of responses pursuant to the provisions of 10 CFR 50.54(f). By letters dated June 10 and July 7, 2011 (ADAMS Accession Nos. ML11164A266 and ML11192A032, respectively), Nebraska Public Power District, the licensee, provided its responses to the bulletin for Cooper Nuclear Station. Portions of the letter dated July 7, 2011, contain sensitive unclassified non-safeguards information and have been held from public disclosure. By letter dated December 6, 2011 (ADAMS Accession No. ML113390265), the NRC sent the licensee a request for additional information (RAt) on its July 7, 2011. response. The licensee responded to the RAI by letter dated December 20, 2011 (ADAMS Accession No. ML11356A243).
The NRC has reviewed the information submitted by the licensee and concludes that the response to the bulletin is acceptable. As summarized in the enclosure, the NRC staff verified that the licensee provided the information requested in the bulletin. No further information or actions under the bulletin are requested.
B. O'Grady - 2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea. wilkins@nrc.gov.
~_IY_'--+-~~
Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
As stated cc w/encl: Distribution via Listserv
SUMMARY
OF NRC REVIEW OF LICENSEE'S RESPONSES TO NRC BULLETIN 2011-01, "MITIGATING STRATEGIES" NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. SO-298
1.0 INTRODUCTION
On May 11, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Bulletin 2011-01, "Mitigating Strategies" (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML 1112S0360), to all holders of operating licenses for nuclear power reactors, except those that have permanently ceased operation and have certified that fuel has been removed from the reactor vessel. The bulletin required two sets of responses pursuant to the provisions of with Title 10 of the Code of Federal Regulations (10 CFR) Section SO.S4(f). The first responses were due 30 days after issuance of the bulletin. By letter dated June 10, 2011 (ADAMS Accession No. ML11164A266), Nebraska Public Power District (the license) provided its response for Cooper Nuclear Station (Cooper) to this first set of questions (first response).
The second responses were due 60 days after issuance of the bulletin. By letter dated July 7, 2011 (ADAMS Accession No. ML11192A032), the licensee provided its response to this second set of questions (second response). Portions of the letter dated July 7, 2011, contain sensitive unclassified non-safeguards information and have been held from public disclosure. By letter dated December 6, 2011 (ADAMS Accession No. ML 11339026S), the NRC sent the licensee a request for additional information (RAI) on its July 7,2011, response. The licensee responded to the RAI by letter dated December 20, 2011 (ADAMS Accession No. ML 113S6A243). As summarized below, the NRC staff has verified that the licensee provided the information requested in the bulletin.
2.0 BACKGROUND
On February 2S, 2002, the NRC issued EA-02-026, "Order for Interim Safeguards and Security Compensatory Measures" (ICM Order) (ADAMS Accession No. ML020S1063S). Section B.S.b of the ICM Order required licensees to develop specific guidance and strategies to maintain or restore core cooling, containment, and spent fuel pool cooling capabilities using readily available resources (equipment and personnel) that can be effectively implemented under the circumstances associated with the loss of large areas of the plant due to explosions or fire.
By letter dated August 9,2007 (ADAMS Accession No. ML072180007), the NRC staff issued its safety evaluation (SE) to document the final disposition of information submitted by the licensee regarding Section B.S.b of the ICM Order. Along with the SE, the staff issued a conforming license condition to incorporate the B.S.b mitigating strategies into the licensing basis.
On March 27,2009, the NRC issued 10 CFR SO.S4(hh)(2) as a new rule, in order to capture the B.S.b mitigating strategies and related license conditions as regulatory requirements for both Enclosure
- 2 current and future licensees. At that time, licensee compliance with the conforming license conditions was sufficient to demonstrate compliance with 10 CFR SO.S4(hh)(2) (74 FR 13926; March 27, 2009), so no further actions were required on the part of current licensees.
3.0 30-DAY REQUEST In order to confirm continued compliance with 10 CFR SO.S4(hh)(2), the bulletin requested that licensees address the following two questions within 30 days of issuing the bulletin:
- 1. Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?
- 2. Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?
The NRC staff reviewed the licensee's first response to determine if it had adequately addressed these questions.
3.1 Question 1: Availability and Capability of Equipment In its first response, the licensee confirmed that the equipment it needs to execute the 10 CFR SO.S4(hh)(2) mitigating strategies is available and capable of performing its intended function. The NRC staff verified that this confirmation covered equipment needed for each of the three phases of B.S.b mitigation strategies. Therefore, the NRC staff concludes that the licensee has adequately responded to Question 1.
3.2 Question 2: Guidance and Strategies Can Be Executed In its first response, the licensee confirmed that the guidance and strategies it has implemented for 10 CFR SO.S4(hh)(2) are capable of being executed considering the current facility configuration, staffing levels, and staff skills. Since the licensee has considered its current facility configuration, staffing levels, and staff skills, and confirmed that it can execute its implemented guidance and strategies, the NRC staff concludes that the licensee has adequately responded to Question 2.
4.0 60-DAY REQUEST The bulletin required a response to the following five questions within 60 days of issuing the bulletin:
- 1. Describe in detail the maintenance of equipment procured to support the strategies and guidance required by 10 CFR SO.S4(hh)(2) in order to ensure that it is functional when needed.
- 2. Describe in detail the testing of equipment procured to support the strategies and guidance required by 10 CFR SO.S4(hh)(2) in order to ensure that it will function when needed.
- 3
- 3. Describe in detail the controls for assuring that the equipment is available when needed.
- 4. Describe in detail how configuration and guidance management is assured so that strategies remain feasible.
S. Describe in detail how you assure availability of offsite support.
The NRC staff reviewed the licensee's second response to determine if it had adequately addressed these questions. The staff also reviewed the NRC's SE dated August 9,2007, to determine what equipment, training, and offsite resources at Cooper were relied upon by the NRC staff to conclude that the licensee's actions would ensure compliance with Section B.S.b of the ICM Order and the conforming license condition.
4.1 Questions 1 and 2: Maintenance and Testing of Equipment Questions 1 and 2 of the 60-day request required licensees to describe in detail the maintenance and testing of equipment procured to support the strategies and guidance required by 10 CFR SO.S4(hh)(2) in order to ensure that it is functional when needed. In its second response, the licensee listed the equipment used to support the 10 CFR SO.54(hh)(2) mitigating strategies which receives maintenance or testing. For each item, the licensee described the maintenance and testing performed, including the frequency and basis for the maintenance or testing activity.
The NRC staff verified that the licensee listed equipment that typically requires maintenance or testing which was relied upon to make conclusions in the SE or commonly needed to implement the mitigating strategies. In its second response, the licensee stated that the portable pump, portable power supplies, compressed gas bottles, hoses, spray nozzles, and communications equipment receive maintenance or testing. The NRC staff noted that the fuel level for the portable pump is verified as part of periodic testing. The licensee also identified other items that support the mitigating strategies that receive maintenance or testing.
The NRC staff verified that the licensee described the process used for corrective actions and listed the testing performed to ensure that the strategies were initially feasible. The licensee stated in its second response that its 10 CFR Part SO, Appendix B, corrective action program is used to document equipment failure, establish priorities, and perform trending.
Based on the above, the NRC staff concludes that the licensee has provided the information requested by Questions 1 and 2.
4.2 Question 3: Controls on Equipment Question 3 of the 60-day request required licensees to describe in detail the controls on equipment, such as inventory requirements, to ensure that the equipment is available when needed. A list of inventory deficiencies and associated corrective actions to prevent loss was also requested.
-4 The NRC staff verified that the licensee described its process for ensuring that B.5.b equipment will be available when needed. In its second response, the licensee identified equipment included in its inventory, the inventory frequency, storage requirements, and items verified.
Items verified include proper quantity, location, and accessibility of equipment. The licensee stated that at the time of its second response there were no outstanding inventory deficiencies that would render the strategies not viable.
The NRC staff verified that the licensee inventoried equipment which was relied upon to make conclusions in the SE or commonly needed to implement the mitigating strategies. In its second response, the licensee stated that procured non-permanently installed B.5.b equipment is inventoried in accordance with station procedures. The second response specifically states that the following items are included in the inventory: portable pump; portable power supply; hoses; communications equipment; spray nozzles; connectors; tools; and instruments. In its RAI response, the licensee described how it ensures the availability of firefighter turnout gear and a vehicle to move the portable pump. The licensee also identified other items that support the mitigating strategies that are inventoried.
Based on the above, the NRC staff concludes that the licensee has provided the information requested by Question 3.
4.3 Question 4: Configuration and Guidance Management Question 4 of the 60-day request required licensees to describe in detail how configuration and guidance management is assured so that the strategies remain feasible.
The NRC staff verified that the licensee described its measures to evaluate plant configuration changes for their effects on the mitigating strategies and to ensure its procedures are current.
In its second response, the licensee stated that plant configuration changes are procedurally required to be evaluated against the licensing basis, which includes the B.5.b mitigating strategies. The licensee stated that the design change process requires a review of affected procedures and that procedure changes are reviewed or validated to ensure that the B.5.b mitigating strategies remain viable.
The NRC staff verified that the licensee described measures it has taken to validate the procedures or guidelines developed to support the mitigating strategies. In its second response, the licensee identified testing in response to Question 2 that demonstrated the ability to execute some strategies. In addition, the licensee stated that "initially, mitigating strategies were validated by demonstrations, walkdowns, engineering evaluations, and/or table top reviews" and they were similarly revalidated in 2011.
The NRC staff verified that the licensee described the training program implemented in support of the mitigating strategies and how its effectiveness is evaluated. In its second response, the licensee identified the training provided to its operations personnel; emergency response organization, including key decision makers; security personnel; and fire brigade. The licensee also identified the frequency with which each type of training is provided and the methods for training evaluating.
Based on the above, the NRC staff concludes that the licensee has provided the information requested by Question 4.
-5 4.4 Question 5: Offsite Support Question 5 of the 50-day request required licensees to describe in detail how offsite support availability is assured.
The NRC staff verified that the licensee listed the offsite organizations it relies upon for emergency response, including a description of agreements and related training. The NRC staff compared the list of offsite organizations that the licensee provided in its second response with the information relied upon to make conclusions in the SE. The licensee stated that it maintains identified the training provided to its operations personnel; emergency response organization, including key decision makers; security personnel; and fire brigade. The licensee also identified the frequency with which each type of training is provided and the methods for training evaluating.
Based on the above, the NRC staff concludes that the licensee has provided the information requested by Question 5.
5.0 CONCLUSION
As described above, the NRC staff has verified that the licensee has provided the information requested in Bulletin 2011-01. Specifically, the licensee responded to each of the questions in the bulletin, as requested. The NRC staff concludes that the licensee has completed all of the requirements of the bulletin for Cooper and no further information or actions under the bulletin are needed.
B. O'Grady - 2 If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea. wilkins@nrc.gov.
Sincerely, IRAJ Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-298
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
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- bry memo d ae FICE NRR/LPL4/PM NRR/LPL4/LA NRRIDPR/PGCB/BC NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins JBurkhardt KMorgan-Butler* MMarkley LWilkins DATE 6/22/12 6/21/12 6/8112 6/26/12 6/26/12 OFFICIAL RECORD COPY