ML100910309
| ML100910309 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/07/2010 |
| From: | Thadani M C Plant Licensing Branch IV |
| To: | Heflin A C Union Electric Co |
| Thadani, M C, NRR/DORL/LPL4, 415-1476 | |
| References | |
| TAC ME3595 | |
| Download: ML100910309 (13) | |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 7, 2010 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251 CALLAWAY PLANT, UNIT 1 -INDIVIDUAL NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR HEARING (EXIGENT CIRCUMSTANCES) (TAC NO. ME3595)
Dear Mr. Heflin:
The U.S. Nuclear Regulatory Commission has forwarded the enclosed "Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing," to the Office of the Federal Register for publication.
This notice relates to your application dated March 29, 2010 (ULNRC-05687), as supplemented by letter dated March 29, 2010 (ULNRC-05690) in which you requested approval of changes to Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," function 6.g, Condition J, and Required Actions J1 and J2; on an exigency basis in accordance with paragraph 50.91 (a)(6) of Title 10 of the Code of Federal Regulations.
If you have any questions, please contact me at 301-415-1476, or e-mail mohan.thadani@nrc.gov.
Sincerely, Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
Notice of cc w/encl: Distribution via
UNITED STATES NUCLEAR REGULATORY UNION ELECTRIC DOCKET NO. NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. NPF-30, issued to Union Electric Company (the licensee), for operation of the Callaway Plant, Unit 1, located in Callaway County, Missouri.
The proposed amendment would revise the Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," regarding function 6.g in TS Table 3.3.2-1. Function 6.g provides an auxiliary feedwater (AFW) start signal that is provided to the motor-driven AFW pumps in the event of a trip of both turbine-driven main feedwater (MFW) pumps. The changes would revise Condition J for ESFAS instrumentation function 6.g to read, "One or more Main Feedwater Pumps trip channel(s) inoperable." The licensee will make corresponding changes to Required Action J.1 and the Note above Required Actions J.1 and J.2 for consistency with the revised Condition.
In accordance with the requirements of paragraph 50.91 (a)(6) of Title 10 of the Code of Federal Regulations (10 CFR), the licensee requested approval of the amendment on exigent basis. The licensee stated that exigent approval was needed due to the time-critical nature of the requested amendment.
The licensee requested approval of the amendment by May 14, 2010. The exigency arises due to the fact that, in the absence of approval of the amendment to TS 3.3.2, if the running MFW pump were to trip, Callaway Plant, Unit 1, will not be able to
-2 resume operation to the plant's licensed power level upon restart from its refueling outage 17, scheduled to end on May 14, 2010. Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations.
Pursuant to 10 CFR 50.91 (a)(6), for amendments to be granted under exigent circumstances, the NRC staff must determine that the amendment request involves no significant hazards consideration.
Under the Commission's regulations in 10 CFR Section 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91 (a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: [Union Electric Company] has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," Part 50.92( c), as discussed below: Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No. Overall protection system performance will remain within the bounds of the previously performed accident analyses since no design changes are proposed to the protection systems. The same reactor trip system (RTS) and engineered safety feature actuation system (ESFAS) instrumentation will continue to be used. The protection systems will continue to function in a manner consistent with the credited functions in the plant design and analysis basis. There will be no changes to the protection system surveillance and operating limits.
-3 The proposed changes will not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, and configuration of the facility or the manner in which the plant is operated and maintained.
The proposed changes will not alter or prevent the ability of structures, systems, and components (SSCs) from performing their intended functions to mitigate the consequences of an initiating event within the assumed acceptance limits. Therefore, the proposed changes will have no impact on the probability of occurrence of an accident previously evaluated in the FSAR [Final Safety Analysis Report]. The transients and design basis events for which the initiation of the AFW system is credited are the main steam line break, loss of non-emergency AC [alternating current] power, loss of normal feedwater, main feed line break, and small break loss of coolant accident.
The analyses of these events in FSAR Chapter 15 assume actuation of the AFW system due to a loss of offsite power signal (starts the turbine-driven AFW pump only), steam generator water level low-low signal (starts the motor-driven AFW pumps for low level in one steam generator, and starts the turbine-driven AFW pump for low level in two steam generators), or a safety injection signal (starts the motor-driven AFW pumps). The anticipatory driven AFW pump auto-start signals from the turbine-driven MFW pumps are not credited in any design basis accidents and are, therefore, not part of the primary success path for postulated accident mitigation as defined by 10 CFR 50.36(c)(2)(ii), Criterion
- 3. Modifying TS 3.3.2 Condition J and its Required Actions for ESFAS instrumentation function 6.g will not impact any previously evaluated design basis accidents.
All accident analysis acceptance criteria will continue to be met with the proposed changes. The proposed changes will not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated.
The proposed changes will not alter any assumptions or change any mitigation actions in the radiological consequence evaluations in the FSAR. The applicable radiological dose acceptance criteria will continue to be met. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No. The proposed changes would provide a TS Condition for more than one inoperable channel within ESFAS instrumentation function 6.g. These
-changes involve an anticipatory motor-driven AFW pump auto-start function that is not credited in any accident analysis.
The proposed changes do not affect the credited ESFAS functions that actuate AFW due to a loss of offsite power, steam generator water level low-low, or a safety injection signal. The proposed changes will not affect the normal method of plant operation or change any operating parameters.
No equipment performance requirements will be affected.
The proposed changes will not alter any assumptions made in the safety analyses.
No new accident scenarios, transient precursors, failure mechanisms, or limiting single failures will be introduced as a result of this amendment.
There will be no adverse effect or challenges imposed on any related system as a result of this amendment.
The proposed amendment will not alter the design or performance of the 7300 Process Protection System, Nuclear Instrumentation System, Solid State Protection System, BOP [Balance of Plant] ESFAS, MSFIS [Main Steam and Feed Isolation System], or LSELS [Load Shedding and Emergency Load Sequencing]
used in the plant protection systems. Therefore, the proposed changes do not create the possibility of a new or different
[kind of] accident from any accident previously evaluated. Does the proposed change involve a significant reduction in a margin of safety? Response:
No. The proposed changes involve the automatic start of the motor-driven AFW pumps after a trip of both turbine-driven MFW pumps which is not a credited start signal for any design basis event. This change does not modify any values or limits involved in a safety-related function or accident analysis.
There will be no effect on those plant systems necessary to assure the accomplishment of protection functions.
There will be no impact on the overpower limit, departure from nucleate boiling ratio (DNBR) limits, heat flux hot channel factor (Fa), nuclear enthalpy rise hot channel factor (Ff1H), loss of coolant accident peak cladding temperature (LOCA PCT), peak local power density, or any other margin of safety. The applicable radiological dose consequence acceptance criteria will continue to be met. The proposed changes do not eliminate any surveillances or alter the frequency of surveillances required by the Technical Specifications.
No
-5 instrument setpoints or system response times are affected. None of the acceptance criteria for any accident analysis will be changed. The proposed changes will have no impact on the radiological consequences of a design basis accident.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied.
Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed determination.
Any comments received within 14 days after the date of publication of this notice will be considered in making any final determination.
Normally, the Commission will not issue the amendment until the expiration of the day notice period. However, should circumstances change during the notice period, such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 14-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration.
The final determination will consider all public and State comments received.
Should the Commission take this action, it will publish in the Federal Register a notice of issuance.
The Commission expects that the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the Chief, Rulemaking and Directives Branch (ROB), TWB-05-B01 M, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this Federal Register notice. Written comments may also be faxed to the ROB at 301-492-3446.
Documents may be examined, and/or copied for a fee,
-6 at the NRC's Public Document Room, located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
Within 60 days of this notice, any person(s) whose interest may be affected may file a request for hearing/petition to intervene.
As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the requestor/petitioner in the proceeding, and how that interest may be affected by the results of the proceeding.
The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements:
- 1) the name, address, and telephone number of the requestor or petitioner;
- 2) the nature of the requestor's/petitioner's right under the Act to be made a party to the proceeding;
- 3) the nature and extent of the requestor's/petitioner's property, financial, or other interest in the proceeding; and 4) the possible effect of any decision or order which may be entered in the proceeding on the requestor's/petitioner's interest.
The petition must also identify the specific contentions which the requestor/petitioner seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted.
In addition, the requestor/petitioner shall provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The requestor/petitioner must also provide references to those specific sources and documents of which the requestor/petitioner is aware and on which the requestor/petitioner intends to rely to establish those facts or expert opinion. The requestor/petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration.
The contention must be one which, if
-7 proven, would entitle the requestor/petitioner to relief. A requestor/petitioner who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing. If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration.
The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment.
If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
All documents filed in NRC adjudicatory proceedings, including a request for hearing, a petition for leave to intervene, any motion or other document filed in the proceeding prior to the submission of a request for hearing or petition to intervene, and documents filed by interested governmental entities participating under 10 CFR 2.315(c), must be filed in accordance with the NRC E-Filing rule (72 FR 49139, August 28, 2007). The E-Filing process requires participants to submit and serve all adjudicatory documents over the internet, or in some cases to mail copies on electronic storage media. Participants may not submit paper copies of their filings unless they seek an exemption in accordance with the procedures described below. To comply with the procedural requirements of E-Filing, at least ten (10) days prior to the filing deadline, the participant should contact the Office of the Secretary bye-mail at
-8 hearing.docket@nrc.gov, or by telephone at (301) 415-1677, to request (1) a digitallD certificate, which allows the participant (or its counselor representative) to digitally sign documents and access the E-Submittal server for any proceeding in which it is participating; and (2) advise the Secretary that the participant will be submitting a request or petition for hearing (even in instances in which the participant, or its counselor representative, already holds an NRC-issued digitallD certificate).
Based upon this information, the Secretary will establish an electronic docket for the hearing in this proceeding if the Secretary has not already established an electronic docket. Information about applying for a digitallD certificate is available on NRC's-public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html.
System requirements for accessing the E-Submittal server are detailed in NRC's "Guidance for Electronic Submission," which is available on the agency's public Web site at help/e-submittals.html.
Participants may attempt to use other software not listed on the Web site, but should note that the NRC's E-Filing system does not support unlisted software, and the NRC Meta System Help Desk will not be able to offer assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC in accordance with the E-Filing rule, the participant must file the document using the NRC's online, Web-based submission form. In order to serve documents through EIE, users will be required to install a Web browser plug-in from the NRC Web site. Further information on the Web-based submission form, including the installation of the Web browser plug-in, is available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a docket has been created, the participant can then submit a request for hearing or petition for leave to intervene.
Submissions should be in Portable Document Format (PDF) in accordance with NRC guidance
-9 available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.htmI.Afiling is considered complete at the time the documents are submitted through the NRC's E-Filing system. To be timely, an electronic filing must be submitted to the E-Filing system no later than 11 :59 p.m. Eastern Time on the due date. Upon receipt of a transmission, the E-Filing system time-stamps the document and sends the submitter an e-mail notice confirming receipt of the document.
The E-Filing system also distributes an e-mail notice that provides access to the document to the NRC Office of the General Counsel and any others who have advised the Office of the Secretary that they wish to participate in the proceeding, so that the filer need not serve the documents on those participants separately.
Therefore, applicants and other participants (or their counselor representative) must apply for and receive a digitallD certificate before a hearing request/petition to intervene is filed so that they can obtain access to the document via the E-Filing system. A person filing electronically using the agency's adjudicatory E-Filing system may seek assistance by contacting the NRC Meta System Help Desk through the "Contact Us" link located on the NRC Web site at http://www.nrc.qov/site-help/e-submittals.html.by e-mail at MSHD.Resource@nrc.qov, or by a toll-free call at (866) 672-7640.
The NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not submitting documents electronically must file an exemption request, in accordance with 10 CFR 2.302(g), with their initial paper filing requesting authorization to continue to submit documents in paper format. Such filings must be submitted by: (1) first class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or expedited delivery service
-to the Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention:
Rulemaking and Adjudications Staff. Participants filing a document in this manner are responsible for serving the document on all other participants.
Filing is considered complete by first-class mail as of the time of deposit in the mail, or by courier, express mail, or expedited delivery service upon depositing the document with the provider of the service. A presiding officer, having granted an exemption request from using Filing, may require a participant or party to use E-Filing if the presiding officer subsequently determines that the reason for granting the exemption from use of E-Filing no longer exists. Documents submitted in adjudicatory proceedings will appear in NRC's electronic hearing docket which is available to the public at http://ehd.nrc.gov/EHD Proceeding/home.asp, unless excluded pursuant to an order of the Commission, or the presiding officer. Participants are requested not to include personal privacy information, such as social security numbers, home addresses, or home phone numbers in their filings, unless an NRC regulation or other law requires submission of such information. With respect to copyrighted works, except for limited excerpts that serve the purpose of the adjudicatory filings and would constitute a Fair Use application, participants are requested not to include copyrighted materials in their submission.
Petitions for leave to intervene must be filed no later than 60 days from [INSERT DATE OF PUBLICATION IN FEDERAL REGISTER].
Non-timely filings will not be entertained absent a determination by the presiding officer that the petition or request should be granted or the contentions should be admitted, based on a balancing of the factors specified in 10 CFR 2.309(c)( 1)(i)-(viii).
For further details with respect to this exigent license application, see the application for amendment dated March 29, 2010, as supplemented by letter dated March 29, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
-11 ML 100880430 and ML 100890460, respectively), which are available for public inspection at the Commission's Public Document Room (PDR), located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
PUblicly available records will be accessible electronically from the ADAMS Public Electronic Reading Room on the Internet at the NRC web site http://www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, or 301-415-4737, or by e-mail to pdr.resource@nrc.gov.
Attorney for licensee:
John O'Neill, Esq., Pillsbury Winthrop Shaw Pittman LLP, 2300 N Street, N.W., Washington, D.C. 20037. Dated at Rockville, Maryland, this t h day of April 2010. FOR THE NUCLEAR REGULATORY COMMISSION Mohan C. Thadani, Senior Project Manager Plant Licensing Branch LPL4 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation April 7, 2010 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251 CALLAWAY PLANT, UNIT 1 -INDIVIDUAL NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR HEARING (EXIGENT CIRCUMSTANCES) (TAC NO. ME3595)
Dear Mr. Heflin:
The U.S. Nuclear Regulatory Commission has forwarded the enclosed "Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing," to the Office of the Federal Register for publication.
This notice relates to your application dated March 29, 2010 (ULNRC-05687), as supplemented by letter dated March 29, 2010 (ULNRC-05690) in which you requested approval of changes to Technical Specification (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," function 6.g, Condition J, and Required Actions J1 and J2; on an exigency basis in accordance with paragraph 50.91 (a)(6) of Title 10 of the Code of Federal Regulations.
If you have any questions, please contact me at 301-415-1476, or e-mail mohan.thadani@nrc.gov.
Sincerely, IRA! Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
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