ML20082Q636
| ML20082Q636 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/06/1991 |
| From: | Mccabe B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082Q638 | List: |
| References | |
| NUDOCS 9109130010 | |
| Download: ML20082Q636 (10) | |
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7590-01 ff3.TJp,,5,Tp,T[,5, pp,C[f pf, fJpp,L,A,T,03,Y, C0t1M1 SS 10N BAI.TItt0RE CAS At!D ELECTPIC COMPANY-0_0,C,KET NOS. 50-317 AND 50-318 NOT I C E O F,,CO N,SJ 0,E R,A,TJ O N, Of, J S,Sp,Ay,C E, O F A,M,Eppp,E N,T,,TO ft.CJ!JI.Y,,0f EF,A,TJ pp, [J,C,EF,5,E,, ffpf 9S,Ep, pp,,5J p!O F 1 C ANT H AZARD S C0t SIDERAT10tl,pE,TERpj NA,TJ0p,,, App,p,P,Pp,RJpp],Ty, F03,yJpfJpp The U.S. f:uclear Regulatory Commission (the Commission) is considering issuance of an amendnent to Facility Operating 1.icense Nos. OPR-53 and DPR-69 issued'to Ealtimore Gas and Electric Company (the licensee) for operation of the Calvert Cliffs Nuclear Pown Plant, Units 1 and 2 located in Calvert County, tiaryland.
The proposed amendment would_ allow the removal of the dedicated Class IE shared emergency power source from a shutdown unit for seven days. The current Technical Sracifications (TS) ar structured so that the shared No.12 Emergency Diesel Generator (EDG) cannot be removed from service for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> without both Calvert Cliffs units being shutdown. The licensee is j
required to remove No.12 EDG from service on October 18, 1991, to perform the
-inspection and maintenance activities required by TS a,8.1.1.2.d.1.
The licensee's current maintenance policy recommends that. 7 days be allotted to conduct the inspection and maintenance activities in a quality manner. To facilitate this and certain other required maintenance and surveillance testing, the licensee will shut down one unit before the current surveillance-t.
interval for the flo. IP EDG expires. The operating unit requires _two Class 1E emergency power sources to be operable. The operable-dedicated diesel from the 9109130010 910906 PDR ADOCK 05000317 P
PDR 1
. shutdown unit will te aligned to the operating unit during the time that the flo.17 EDG is out of service. Corrensatory measures will be taken for the shutdcwn unit to provide assurance that A.C. electrical pcwer will be available to the eouipr:ent necessary to maintain the shutdown unit in a safe condition durirg this scheduled maintenance interval.
Specifically, the proposed changes will modify TS Sections 3.8.1.2,
" ELECTRICAL F0WER $YSTEMS - SHUTDOWN", and 3.B.T,?, "A.C. DISTRIBUTION -
SHUTDOWN", for both units. The TS change provides for a special test exception from the present requirement for an operable EDG on the shutdown unit, and will allow'the dedicated EDG from the shutdown unit to be aligned to the operating unit.
Compensatory measures which will be taken for the shutdown unit included in the proposed TS changes are:
Either two 500 kV offsite power circuits or one 500 kV offsite power circuit and the 69 kV Southern Maryland Electric Cooperative (SMECO) offsite power circuit shall be verified available and the availability confirmed once per shift; Core alterations, positive reactivity changes, movement of irradiated fuel and_ movement of heavy loads over irradiated fuel w,:1 be suspended, and containment penetration closure will be established; and
- A temporary diesel generator capable of carrying the shutdown unit's A.C.
electrical loads will be verified available.
If these conditions are not met, then 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> are allotted to restore availability of the temporary diesel. generator and the off-site power l.
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If they are not made available within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then an operable EDG must be aligned to the shutdown unit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. This will place the operating unit in TS ACTION statement 3.8.1.1.b (lack of two EDGs) which allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore two operable EDGs or be in hot standby in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The TS Bases are also modified to support the above proposed changes.
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. 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.
The Commission has made a proposed determination 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 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 (?) 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
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presented below:
(1) Would not involve a significant increase in the probability or consequences of an accident previously evaluated.
This change was. evaluated'to determine its impact on the probability or consequences of a loss of offsite power event, a boren dilution event, and a fuel handling-incident. The baron dilution event and the fuel handling incident are the only two accidents that are explicitly analyzed in the Updated Final Safety Analysis Report (UFSAR) for a shutdown unit.
There is a very low probability of occurrence of a loss of offsite power during the seven day period that No.12 Emergency Diesel Generator (EDG) would be out of service for inspection _and maintenance. This configuration will only be required until two additional Class 1E EDGs (one for each unit) will Le installed (about February _1995) as part of BG&E's implementation of the Station Blackout Rule (10 CFR 50-63).
These new EDGs would provide sufficient flexibility for scheduling and performing maintenance such that this relief from technical specification requirements will no longer be needed.
To ensure a low probability of a loss of offsite power, BG&E has reviewed potential precursors such as weather events and onsite work activities. The Calvert Cliffs offsite power supply is designed to be diverse and redur. dant, and is therefore inherently capable of l
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4 withstanding severe weather events, in addition, BG&E's Emergency Response Plan already requires that certain actions be taken, up to and including shutdown of both units, on the approach of a severe storm.
As regards work-related events, the probability of a loss of offsite power is maintained low by prohibiting planned maintenance on the two 500 kV transmission lines and in the switchyard.
Availability of the independent offsite power source, the 69 kV Southern Maryland Electric Cooperative (SPECO) feeder, will be verified once per shift.
This requirement to maintain two available qualified offsite power sources compares favorably with tre requirements of the current technical specifications to maintain only one offsite source to the shutdown unit.
A temporary diesel generator will also be installed to provide a backup onsite source of power capable of supporting necessary safety-related loads.
Finally, potential accident precu-sors such as core alterations, positive reactivity insertions, movement of irradiated fuel, and rr.ovement of heavy loads over irradiated fuel will be prohibited while No. 12 EDG is out of service. Therefore, the probability of a boron dilution event or fuel bandling incident is decreased during the.
operations-allowed by this change.
The requirement to maintain containment penetration closure while No. 12 EDG is out of service ensures that the consequences of an accident would not be significantly increased.
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 or different type of accident from any accident previously evaluated.
A temporary diesel generator is being iostalled onto the 4 kV bus of a shutdown (Mode 5 or 6) unit while the dedicated EDG for this unit is. transferred for up to seven days to the operating unit.
This configuration allows the performance of inspection and maintenance required by Technical Specification 4.8.1.1.2.d.1 for No. 12 EDG.
This change has been evaluated and it has been determined that this installation does not impair any existing _
safety-related equipment needed to maintain the unit in a safe shutdown condition. Differences in the operation of the temporary diesel generator and the permanent EDGs include manual starting of the temporary diesel generator and manual loading of the 4 kV bus.
These operations are not significantly different from typical operator activities.
' Therefore, the proposed changes would 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 operability of the minimum specified A.C. and D.C. electrical power sources and associated distribution systems during Modes 5 and 6 ensure that; 1) the unit can be maintained in Mode 5 or 6 for extended time periods and, 2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.
The proposed change does not affect the D.C. power sources or the A.C. and D.C. distribution systems, it affects only the A.C.
power sources in that we are removing the emergency A.C. power source from the shutdown unit for seven days. This change will have no impact on the offsite power sources.
Compensatory measures will be taken for the loss of the emergency power source. They are:
o requiring that two offsite power sources are available, o
core alterations, positive reactivity changes, movement of irradiated fuel, and movement of heavy loads over irradiated fuel will be suspended, and o
containment penetration closure will be established.
These compensatory measures reduce the potential for a loss of offsite power, a fuel handling accident, and a boron dilution event during the seven days that the emergency power source is not available to the shutdown unit.
Additionally, we are providing a temporary diesel generator capable of supplying the 1.oads necessary -
to maintain the unit in a safe condition. These measures, along with the infrequent need to enter this condition, ensure that the margin of safety is not significantly reduced.
Therefore, the proposed change would not involve a significant reduction in the margin of safety.
i 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.
t The Commission is seeking putlic comments on this proposed determination.
Any comments received within thirty (30) days af ter the date of publication of l
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6-this notice will be considered in making any final determination.
The Ccnrission will not nornially make a final determination unless it receives a request for a hearing.
Written ccnnents nay be submitted by mail to the Regulatory Publications 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 nun.ber of this FEDERAL REGISTER notice. Written cornents may also be delivered to Room P-223, Phillips Building, 7920 Norfolk Avenue, Bethesda, Maryland, from 7:30 a.m. to 4:15 p.m.
Copies of written comments received may be examined at the NRC Public Document Room, the Gelman Building, 2120 L Street, NW., Kashington, DC 20555. The filing of requests for hearing and petitions for leave to intervene is discussed below.
By October 15, 1991
, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interes+
y be affected by this proceeding and who wishes to participate as a pai j 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 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 Commission's Public Document Room, the Gelman Euilding, 2120 L Street, NW., Washington, DC 20555 and at the local public document room located at the Calvert County Library, Fourth Street, P.O. Box 405, 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 e
. 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 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 fifteen (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 fifteen (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.
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,. In addition, the petitioner shall provide a brief explanation of the bases of the contention and a concise statement of the ally ed 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 4
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aware and on whirb 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 amendnent 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 t,e 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 immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of-the amendment.
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If the final determination is that the anendrent request involves a significant ha:ards consideration, any hearing held would take place before the issuance of any amendment, t:orn; ally, the Consnission will not issue the amendment until the expiration of the 30-day notice period. Powever, 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 f acility, the Co'aission may issue the license amendment before the exptiation of the 30-day rotice 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 and provide for opportunity for a hearing af ter issuance. The Commission expects that the need to take this action will occur very infrequently.
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, 4
Washington, DC 20555, Attention: Docketing and Services Branch, or may be delivered to the Consission'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 ten (10) days of the notice period, it is requested-that the petitioner promptly so inform the Commission by a toll-free telephone call 4
to Western Union at 1-(800) 325-6000 (in Missouri 1-(800)342-6700). The Western Union operatur should be given Catagram Identification Number 3737 and the following message addressed to Robert A. Capra: petitioner's name and telephone number, date petition was mailed, plant name, and publication
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. date and rage number of this FEDERAL REGISTER notice. A copy of the petition shculd elso be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and to Jay E. Silbert, Esquire, Shaw, Pittman, Potts and Trowbridge, 2300 N Street, NW., Washington, DC 20037, 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 ebscrt a determination by the Commission, the presiding officer or the 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) and2.714(d).
For further details with respect to this action, see the application for amendment dated September 5, 1991, which is available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555 and at the local public document room located at the Calvert County Public Lib' ary, Fourth Street, P.O. Box 405, Prince Frederick, Ma ryland 20678.
Dated at Rockville, Maryland, this 6th day of September 1991.
FOR THE NUCLEAR REGULATORY COMMISSION AAM!
t Brian C. McCabe, Acting Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
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September 6, 1991 Docket Nos. 50 317 DISTRIBUTION:
50 318
. D5TclierFTii-DMcDonald NRC/ Local PDR OGC PDI.1 RF ACRS(10)
SVarga GPA/PA Mr. G. C. Creel JCalvo Plant File Vice President - Nuclear Energy RACapra JLinville Daltimore Gas and Electric Company CVogan Calvert Cliffs Nuclear Power Plant MD Rts. 2 & 4 P. O. Box 1635 Lusby, Maryland 20657
Dear Mr. Creel:
SUBJECT:
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENTS FOR THE CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 (TAC NO. 81402)
AND UNIT 2 (TAC NO. 81403)
By letter dated September 5, 1991, you requested amendments to facility Operating License Nos. DPR-53 and DPR-69 for the Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2, respectively. The request is to modify the Technical Specification (TS) Limiting Condition for Operation (LCO) and action requirements to allow for the inspection and maintenance of the shared emergency diesel generator (EDG) No.12 when one unit is operating and the other unit is shutdown. The TS Bases are also changed to support the proposed TS modifications.
Enclosed for your information is a copy of a Notice of Consideration of Issuance of Amendments to the Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing.
The Notice has been forwarde! to the Office of Federal Register for publication.
Sincerely, Brian C. McCabe for r
Daniel G. Mcdonald, Jr., Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Notice cc w/ enclosure:
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Document Name:
CC1/2 LETTER OF CONSIDERATION