ML20046C937
| ML20046C937 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/19/1993 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20046C938 | List: |
| References | |
| NUDOCS 9308130060 | |
| Download: ML20046C937 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION BALTIMORE GAS & ELECTRIC COMPANY DOCKET N0. 50-318 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE. PROPOSED N0 SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. DRP-69, issued to Baltimore Gas & Electric Company (the licensee), for operation of the Calvert Cliffs Nuclear Power Plant, Unit No. 2 located in Calvert County, Maryland.
The proposed amendment would revise Technical Specifications (TS) 3/4.2,
" Power Distribution Limits," and 3/4.3, " Instrumentation," to relax the requirements for the number and distribution of operable incore detectors.
The incore detectors are required to verify that the core power distribution is consistent with the safety assumptions used in the safety analyses and to protect the current power distribution TS limits. The proposed changes would also apply penalties to the values measured by the incore detectors prior to their comparison with TS limits to assure that the TS limits monitored by the incore detectors will continue to be valid.
Specifically, footnotes will be added to the following TS and will be applicable for only the remainder of the Calvert Cliffs Nuclear Power Plant, Unit 1, Operating Cycle 11, as follows:
9308130060 930719 PDR ADDCK 0500031B P
PDR_
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TS 3.2.2.1, Total Planar Radial Peaking Factor, Limiting Condition For Operation (LCO), 3.2.3, Total Integrated Radial Peaking Factor LC0; and i
4.2.1.4.b.1, Surveillance Requirements for Incore Detector Monitoring System will have footnotes indicating that when the percentage of operable incore detector locations (strings) fall below 75%, the measurement-calculational uncertainty factor will be increased by 1% prior to being compared to the TS limits.
TS 4.2.1.4.a, Surveillance Requirements for Incore Detector Monitoring System; 4.2.2.1.2.b, Total Planar Radial Peaking Factor; and 4.2.3.2.b, Total Integrated Radial Peaking Factor, will have footnotes indicating that when the percentage of operable incore detector locations (strings) falls below 75%
the full core power distribution mapping frequency will be increased to at least once per 15 days of accumulated operation while in Operating Mode 1.
TS 3.3.3.2.a, Monitoring Instrumentation LCO, for monitoring Azimuthal Power Tilt will have a footnote which supersedes the current requirement. The current requirement for two quadrant symmetric incore detector segment groups at each axial location is changed to a total of eight quadrant symmetric incore detector segment groups. The current requirement for at least two azimuthal power tilt values at each detector segment axial elevation is changed to at least one azimuthal power tilt value at each detector segment axial elevation and at least two azimuthal power tilt values at three detector segment axial elevations.
TS 3.3.2.b.1, Monitoring Instrumentation LCO, for recalibration of the Excore Neutron Monitoring Flux Detector System; and 3.3.3.2.C.1, Monitoring Instrumentation, for monitoring the Unrodded Planar Radial Peaking Factor, the
. Unrodded Integrated Radial Peaking Factor, or the linear heat rate will have footnotes which will change the minimum number of operable detector segments and strings from 75% to 60%.
Before issuance of the proposed license amendment, the Comission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations.
The Comission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Comission's regulations in 10 CFR 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:
The proposed change has been evaluated against the standards in 10 CFR 50.92 and has been determined to not involve a significant hazards consideration, in that operation of the facility in accordance with the proposed amendments:
1.
Would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change would relax requirements for the number and distribution of operable incore detectors. The safety function of the incore detectors is to verify that the core power distribution is consistent with the assumptions used in the safety analyses.
Sufficient measurements will be required to adequately verify compliance with power distribution Technical Specification limits.
Penalties will be applied to the values measured by the incore i
detectors prior to comparison with the Technical Specifications limits when the number of operable detector strings falls below the i
current requirement. This will ensure that all current Technical Specification and fuel design limits are protected and the core power distribution assumptions in all analyses remain valid. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
Would not create the possibility of a new difference type of accident from any accident previously evaluated.
The proposed change does not represent a change in the configuration or operation of the plant. The current Technical Specifications limits measured by the incore detector system will still be met.
Therefore, the proposed change does not create the possibility of a new or different type of accident from any accident previously evaluated.
3.
Would not involve a significant reduction in a margin of safety.
The proposed changes will continue to protect the current power distribution Technical Specifications limits. When the number of operable incore detector strings falls below the current Technical Specification requirement, a penalty will be added to the measured values before they are compared with the Technical Specification limits. This penalty has been shown by prior analysis to be greater than the increased uncertainty.
This penalty ensures that the Technical Specifications limits monitored using the incore detectors will continue to be protected.
Therefore, the proposed change does 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 30 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 30-day notice period. However, should circumstances
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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 Comission may issue the license amendment before the expiration of the 30-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 coments received.
Should the Comission take this action, it will publish in the FEDERAL REGISTER a notice of issuance and provide for opportunity for a hearing after issuance.
The Comission expects that the need to take this action will occur very infrequently.
Written coments may be submitted by mail to the Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Comission, j
Washington, DC 20555, and should cite the publication date and page number of this FEDERAL REGISTER notice. Written coments may also be delivered to Room-1 P-223, Phillips Building, 7920 Norfolk Avenue, Bethesda, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Copies of written coments received may l
be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555.
j The filing of requests for hearing and petitions for leave to intervene is discussed below.
By August 23, 1993
, the licensee may file a request for a
'l hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must-
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file a written request for a hearing and a petition for leave to intervene.
Requests for a }{ earing and a petition for leave to intervene shall be filed in accordance with the Comission's " Rules of Practice for Domestic Licensing Proceedings" in 10 CFR Part 2.
Interested persons should consult a current copy of 10 CFR 2.714 which is available.at the Comission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, i
DC 20555 and at the local public document room located at Calvert County Library, Prince Frederick, Maryland.
If a request for a hearing or petition for leave to intervene is filed by the above,date, the Comission or' an Atomic Safety and Licensing Board, designated by the Comission or by the Chairman of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
As required by 10 CFR 2.714, a petition for leave to intervene shall set forth with particularity the interest of the 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 t
intervention should be permitted with particular reference-to the following factors:
(1) the nature of the petitioner's right under the Act to be made a party to the proceeding; (2) the nature and extent of the petitioner's property, financial, or other interest in the proceeding; and (3) the possible effect of any order which may be entered-in the proceeding on the petitioner's interest. The petition should also identify. the specific I
. aspect (s) of the subject matter of the proceeding as to which petitioner wishes to intervene. Any person who has filed a petition for-leave to i
intervene or who has been admitted as a party may amend the petition withoutrequestjngleaveoftheBoardupto15dayspriortothefirst prehearing conference scheduled in the proceeding, but such an amended petition must satisfy the specificity requirements described above.
Not later than 15 days prior to the first prehearing conference scheduled in the proceeding, a petitioner shall file a supplement to the petition to intervene which must include a list of the contentions which are sought to be litigated in the matter.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted.
In addition, the petitioner shall provide a brief explanation of the bases of 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 petitioner must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion.
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 proven, would entitle the petitioner to relief. A petitioner who fails to file such a supplement which satisfies 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, including the opportunity;to present evidence and cross-examine witnesses.
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 imediately 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.
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Comission, U.S. Nuclear Regulatory Comission, Washington, DC 20555, Attention: Docketing and Services Branch, or may be delivered to the Comission's Public Document Room, the I
Gelman Building, 2120 L Street, NW., Washington, DC 20555, by the above date. Where petitions are filed during the last 10 days of the notice period, it is requested that the petitioner promptly so inform the Comission by a toll-free telephone call to Western Union at 1-(800) 248-
)
5100 (in Missouri 1-(800) 342-6700). The Western Union operator should be given Datagram Identification Number N1023 and the following message addressed to Robert A. Capra:
petitioner's name and telephone number; date petition was mailed; plant name; and publication date and page number of 1
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this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Off; ice of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and to D. A. Brune, Esq., General Counsel, Baltimore Gas and Electric Company, P.O. Box 1475, Baltimore, Maryland 21203, attorney for the licensee.
Nontimely filings of petitions for leave to intervene, amended petitions, supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the presiding Atomic Safety and Licensing Board that the petition and/or request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
For further details with respect to this action, see the application for amendment dated July 16, 1993, which is available for public inspection at the Comission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555, and at the local public document room, located at Calvert County Library, Prince Frederick, Maryland.
Dated at Rockville, Maryland, this 19th day of July 1993.
FOR THE NUCLEAR REGULATORY COMMISSION ay ek Daniel G. Mcdonald, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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l July 19, 1993 Docket No. 50-318 Mr. Robert. E. Denton Vice President - Nuclear Energy Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-4702
Dear Mr. Denton:
SUBJECT:
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR HEARING, CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 2 (TAC NO. M86965)
The Commission has requested the Office of the Federal Register to publish the enclosed " Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing." This notice relates to'your application for amendment dated July 16, 1993, that requested changes to Technical Specification Sections 3/4.2, " Power Distribution Limits," and 3/4.3, " Instrumentation," relating to incore detector requirements. This notice was published as an " Individual Notice" with a 30-day comment period rather than a " Biweekly Notice" in view of the unpredictability of future in-core detector failures which might result in requiring that Unit 2 be shutdown.
Sincerely, Original signed by:
Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Notice cc w/ enclosure:
See next page Distribution:
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OFFICIAL RECORD COPY FILENAME: G:\\CCl-2\\CC186965.IND
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