ML20035A152
| ML20035A152 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/11/1993 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035A153 | List: |
| References | |
| NUDOCS 9303240187 | |
| Download: ML20035A152 (10) | |
Text
.
I UNITED STATES NUCLEAR REGULATORY COMMISSION BALTIMORE GAS & ELECTRIC COMPANY DOCKET NO. 50-317 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO
~;
FACILITY OPERATING LICENSE. PROPOSED NO 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. 53, issued to Baltimore Gas & Electric Company (the licensee), for operation of l
the Calvert Cliffs Nuclear Power Plant No. I located in Calvert County, i
l t
The proposed amendment would revise Technical Specifications (TS) 3/4.2, i
" 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 I
is consistent with the safety assumptions used in the safety analyses and to protect the current power distribution TS limits. The proposed changes would I
also apply penalties to the valres 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:
i TS 3.2.2.1, Total Planar Radial Peaking Factor, Limiting Condition for i
Operation (LCO), 3.2.3, Total Integrated Radial Peaking Factor LC0; and l
1 9303240187 930311 PDR ADDCK 05000317 1
p PDR l
t I 4.2.1.4.b.1, Surveillance Requirements Incore Detector Monitoring System will have footnotes indicating that when the percentage of operable incore detector locations (strings) fall below 75%, the measured values will be increased by 1% prior to being compared to the TS limits.
TS 4.2.1.4.a, Surveillar e Requirements for incore Detector Monitoring I
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 i
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.
i TS 3.3.3.2.a, Monitoring Instrumentation LCO, for monitoring Azimuthal j
Power Tilt will have a footnote which supersedes the current requirement. The i
current requirement for two quadrant symmetric incore detector segment groups at each axial location is changed to a total of eight quadrant symmetric l
incore detector segment groups. The current requirement for at least two j
i 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.
[
I TS 3.3.3.2.b.1, Monitoring Instrumentation LCO, for recalibration of the l
Excore Neutron Monitoring Flux Detector System; and 3.3.3.2.C.1, Monitoring l
Instrumentation, for monitoring the Unrodded Planar Radial Peaking Factor, the i
Unrodded Integrated Radial Peaking Factor, or the linear heat rate will have i
footnotes which will change the minimum number of operable detector segments and strings from 75% to 60%.
t
> I The licensee states that exigent circumstances pursuant to 10 CFR 50.91 exist with respect to the need for consideration of the proposed amendment.
The need for this change could not have been foreseen in that 19 of the 45 i
incore detector strings were replaced during the previous outage and one was i
removed and not replaced due to mechanical problems.
Each of the incore i
detector strings consists of 4 rhodium neutron detectors (or referred to as l
detector segments) which are located at 20, 40, 60 and 80% of the core height.
I l
Prior to reaching 100% power following the refueling outage, 20 detectors had i
failed.
There have been 8 additional detector failures since reaching 100%
power. All 28 of these detector failures were in the group of new detector strings installed during the outage. Adding the 4 detectors which were not replaced, 32 of the 180 available detectors (17.8%) are inoperable. The TS require that 75% of the detector strings be operable and specific groups be operable for azimuthal power tilt monitoring.
The licensee has performed a Root Cause Analysis, but was unable to l
identify the cause of the detector failures nor account for the unexpected large number of failures of the newly-installed detectors. The licensee further notes that it is impossible to predict when, or if, additional incore l
detector failures will occur. The time between failures has varied from as I
much as 62 days to as little as 10 days. Due to the uncertainty in the i
failure history of the incore detectors during the current operating cycle of
~
Unit 1, the licensee believes that there is insufficient time to allow for the i
normal 30 day public comment period for the requested amendment. On this basis, the staff finds that a condition of exigency exists and is providing a notice period of 15 days in this notice for the receipt of cumments.
I
. l P
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 50.92, this means that operation of the f acility 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 l
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.
1 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 pouer 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 detectors prior to comparison with the Technical Specifications limits when the number of operable detector strings falls below the 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, I
i
r.
[ t 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.
l 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 l
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 15 days after the date of i
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 15-day notice period. However, should circumstances change during the notice period, cch that failure to act in a timely way
E i
would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the I
15-day notice period, provided that its final determination is that the j
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 Rules Review and Directives Branch, Division of Freedom of Information and Publications Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and should cite the publication date and page number of
[
this FEDERAL REGISTER notice. Written comments may also be delivered to Room f
P-223, Phillips Building, 7920 Norfolk Avenue, Bethesda, Maryland, from 7:30 l
a.m. to 4:15 p.m. Federal workdays. Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
By April 19, 1993
, the licensee may file a request for a I
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 file a written request for a hearing and a petition for leave to intervene.
Requests for a hearing and a petition for leave to intervene shall be filed i
i
I
- in accordance with the Commission'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, 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 Commission or an Atomic Safety and Licensing Board, designated by the Commission 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 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 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 intervene or who has been admitted as a party may amend the petition
~ without requesting leave of the Board up to 15 days prior to the first 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 statenent 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 i
I i :
t I
the opportunity to present evidence and cross-examine witnesses.
If the amendment is issued before the expiration of the 30-day hearing period, the Comission will make a final determination on the issue of no significant hazards consideration.
If a hearing is requested, 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 l
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.
j i
A request for a hearing or a petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Docketing and Services Branch, or may be delivered to the Commission's Public Document Room, the 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 Commission 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 Humber N1023 and the following message addressed to Robert A. Capra: petitioner's name and telephone number; I
date petition was mailed; plant name; and publication date and page number i
O.
date petition was mailed; plant name; and publication date and page number of this FEDERAL REGISTER notice. A copy of the petition should also be sent to the Office 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 l
request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
I For further details with respect to this action, see the application j
for amendment dated March 9,1993
, which is available for public i
i inspection at the Commission's Public Document Room, the Gelman Building, 1
2120 L Street, NW., Washington, DC 20555, and at the local public document i
room, located at Calvert County Library, Prince Frederick, Maryland.
Dated at Rockville, Maryland, this 11th day of March.
FOR THE NUCLEAR REGULATORY COMMISSION l
n Daniel G. Mcdonald, Senior Project anager Project Directorate I-I Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation l
I e
b March 11, 1993 Docket No. 50-317 I
Mr. Robert. E. Denton 1
Vice President - Nuclear Energy Baltimore Gas & Electric Company i'
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway i
Lusby, Maryland 20657-4702 l
Dear Mr. Denton:
l
SUBJECT:
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION i
DETERMINATION, AND OPPORTUNITY FOR HEARING, CALVERT. CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 (TAC NO. M85939)
The Commission has requested the Office of the Federal Register to 4
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 March 9,1993, that requested changes to t
Technical Specification Sections 3/4.2, " Power-Distribution Limits" and 3/4.3,
-l
" Instrumentation," relating to incore detector requirements.
This notice was l
published as an " Individual Notice" with a 15-day comment period rather than a
" Biweekly Notice" in view of the exigent nature.of the requested amendment as detailed in the enclosed Notice.
Sincerely, Ori,ginal Signed By:
Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
\\
Enclosure:
Notice j
CC W/ enclosure:
)
See next page i
Distribution:
'l See next page OFFICE PDI-1:LA PDI-1 : PPL_ O PDI-1:D EAME cVogan H DMcDonal N RAcapra
.l5 U/93 3/
3 // /93
/ /
/ /
d 93 can
/
/
/
OFFICIAL RECORD COPY FILENAME: G:\\CCl-2\\CC185939.EXI J
-.