ML20079P839
| ML20079P839 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/21/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079P833 | List: |
| References | |
| NUDOCS 9111140084 | |
| Download: ML20079P839 (5) | |
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WA$mNO10N. D C. M%h s-f SAFETY EVALUATION BY THE OrriCE Of NUCLEAR REACTOR REGUIATION RELATED TO AMENDMENT NO.103 TO FACillTY OPERATING LICENSE NO. DPR-53 AND AMEN 0 MENT NO.14310 FAClllTY OPERATING LICENSE NO. OPR-69 B_ALTIM0RE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR pVWER PLANT, UNIT N05, 1 AND 2 DOCKET N05, 50-317 AND Q-3)8
1.0 INTRODUCTION
By letter dated September 5, 1991, as supplemented September 26, 1991, the Baltimor t. Cas cru. Mectric ump +y (+he licentee) submitted o request for changes to the Calvert Cliffs huclear twer Plant, Unit Nos.1 and 2, TechnicalSpecifications(TS). The requested changes would allow the removal of the dedicated Class lE emergency di+rel generator (EDG) from a shutdown unit and allows its realignment to the operatino init for a period of up to 7 days.
This is net.estery to meet the TS requirer,nt that two Class lE emergency power sources be available for an operating rait and will allow the removal of the shared Class lE No. 12 EDG to permit tne petformance of its required inspections ar.d maintenance.
Specifically, the changes modify TS Scctions 3.8.1.2, " ELECTRICAL 00WER SYSTEMS
- SHUTDOWN", tnd 3.8.2.2, "A.C. DISTRIBUTION - SHUTDOWN", for both units. The TS changes provide for a special test exception from the present requirement for an operable Class 1E EDG on the shutdown unit (Modes 5 and 6).
The choge biso specifies the compensatory measures and actions required to be taken for the shutdown unit, including the availati N of a temporary diesel generator (TDG), during the unavailability of a d G: ateo ' lass IE EDG, The TS Dases are also modified to support the changes. The SeptemL'r 26, 1991, letter provided clarifying information that did not change the instial proposed no significant hazards consideration determination.
2.0 BACr. GROUND By letter dated September 9, 1091, Baltimore Gas and Electric Company (the licensee) requested an Amendment te its Operating License for Calvert Cliffs, Units 1 and 2 to revise Technical Specifications (TS) 3.8.1.2 and 3.8.2.2 to allow the removal of the shared No.12 Class 1E emergency diesel generator (EDG) for a period of up to 7 days.
The licensee requested this amendment t.ecause recent Amendments to the Units 1 and 2 TS 3.8.1.2 and 3.8.2.2 issued on June 27, 1991, do not allow the No. 12 EDG to be removed from service for inspection for more than 7T hours without shutting down both nuclear units 9111140004 911021 PDR ADOCh 05000317 P
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The licensee's traintenance policy now requirer, based on ver.dcr recommendations, that 7 days be allocated to conduct inspection and maintenance activities on the No.12 EDG.
The inspection and maintenance activities are required by Surveillance Requirement 4.8.1.1.2.d.1.
In order to facilitate these activitici on the No.1? EDG and other required maintenance and surveillance testing, the licensee plans to shut down one unit before the current surveillance interval for the No. 12 EDG expires.
The operating unit requires two Class Il energency power sources to be operable.
Tht licensee proposes to align the operable dedicated EDG from the shutdown unit to the operating unit during the time that the shared No. 12 EDG is out of service.
Further, the Licensee proposes to take compensatory measures for the shutdown unit, which includes the use of a temporary diesel generator, to provide assurance that AC electrical power will be available, if needed, to power the necessary equipment to maintain the unit in the shutdown condition upon loss of-the offsite power source.
Given the IP-month surveiliance interval on the No.12 EDG for Surveillance Requirement 4.8.1.1.2.d.1, the licensee anticipates that the No. 12 EDG will be taken out of service under the provisions of this amendment at least three times prior to the installation of the two additional EDGs current y scheduled for February 1995.
3.0 EVALVATION The Calvert Cliffs Nuclear Power Plant emergency AC electrical power configuration consists of three Class IE EDGs. The No. 11 EDG is normally aligned to Unit 1, the No. 21 EDG is normally aligned to Unit 2, and the No. 12 EDG, which is a shared or " swing" diesel generator, may be aligned to either unit. The design also allows for the normally dedicated diesel generator to be aligned to the other unit, i e., the No.11 EDG can be aligned to Unit 2 or the No. 21 EDG can be aligned to Unit 1.
This arrangement allows the shared diesel generator (No. 1; EDG) to be removed from service while still meeting l
the operating requirements of TS 3.8.1.1 (two EDGs. operable in Modes 1, 2, and 3) for one unit. The specific TS changes and nur evaluation are:
Action Statements 3.8.1.2./3.8.2.2 The licensee proposes to change the subject action statements by segregating the existing text into new sections 3.8.1.2.a and 3.8.2.2.a whir.h is to be applicable for periods other than the performance of Surveillance Requirement, 4.8.1.1.2.d.1 on EDG No. 12, Section b is added to Specifications 3.8.1.2 and 3.8.2.2 which specifies the ections to be taken for periods with less than the minimum required AC electrical power sources operabie during the performance of Surveillance Requirement 4.8.1.1.2.d.1 on the No.12 EDG.
Specifically, for
& proposed sections 3.8.1.2.b and 3.8.2.2.t the licensee proposes the following compensatory n;easures:
I
. a.
Either two 500 KV offsite power circuits or one 500 LV pwer circuit and the 69 KY Southern Maryland Electric Cooperative (SMECO) offsite power circuit shall be available during the No. 12 EDG out of service period.
The staff 69u es that the added availabi'ity of the two offsite power circuits provides greater assurance that AC power will be available to the shutdown unit reducing the possibility of a loss of offsite power event similar to the March 1990 Vogtle event. The actions by the licensee to prohibit planned raintenance on the 500 KY transmission lines and in the switchyard as well as verification every 12-hour shift of the availability of the 69 KV SMECO line represent prudent steps to maintain offsi'e power sources to the shutdown unit, further, the licensee's Emetgency Response Plan requiret that certain precautionary actions be taken, up to and including the shutting down of the operating unit.
On the approach of a severe storm these actions reduce the potential for weather-related events from adversely affecting safe operation of both units during the 7 day period, b.
Core alterations, positive reactivity changes, movement of irradiated fuel, and movement of heavy loads over irradiated fuel will be suspended, and containment penetration closure will be established during the No. 12 EDG out of service period.
These measures are taken by the licensee to preclude a fuel handling accident and to reduce the possibility of a boron dilution accident which are the design basis accidents for a shutdown unit.
The containment closure measure provides additional assurance that the cor. sequences of an accident will be mitigated, c.
A temporary diesel generator (lDG) capable of carrying the shutdown unit's /C electrical loads will be available.
The staff has reviewed the installation of the TDG to provide a backup ensite emergency source of power capable of supporting the necessary safety related loads during shutdown as cited in the amendment request.
In addition the staff has met with licensee representatives to obtain additional c,larifying informat ton in the following areas: (1) the details regarding the design, operation, and maintenance of the TDG; (?) the installation details of the TDG prior to and between refuelina outage periods; (3) details of the 50.59 Safety Evaluation which indicates that no impairrhent h65 been created to existing safety-related equipment due to the use of the TOG, and (4) what effects this TS change has on EDG reliability and, therefore, overall plant safety. During the subject discussions,TDG from I hour to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in crder to be consistent with the the licensee agreed to change the period to perform the load i
test on the L
testing methodology used to test the existing EDGs.
In the above mentioned aruas-the staff believes that the licensee has taken appropriate action to prescribe measures to maintain a source of emeroency onsite power should this source be necessary to maintain the shutdown unit in a safe condition, l
I 4
Given the compensatory measures proposed to be taken by the licensee cited in Sections 3.8.1.2.b and 3.8.2.2.b, the estimated small reduction in overall diesel generator reliability and the short interval (7 days) the subject measures are expected to be in force, we find that the TS change, with the TDG load test to be performed for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> rather than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, is acceptable.
Bases 3/4.8 The licensee proposes to reflect the change shown in Specifications 3.8.1.2 and 3.8.2.2 in the TS Bases. The staff finds that this change does not affect the original TS intent, is consistent with the requirement to have minimum specified AC sources during Modes 5 and 6 operable, consistent with the requested changes, and is, therefore, acceptable.
4.0
SUMMARY
We have reviewed the licensee's amendment submittal and have concluded that:
1)theTSchangesforadditionalredundancyinoffsiteACpowersources,
- 2) restrictions on onsite activities which could lead to degraded operating conditions, and 3) the installation of a TDG with appropriate controls durIng the short interval anticipated, do not significantly increase -the risk to the health and safety of the public and is, therefore, acceptable.
In addition, the requested change will allow more thorough inspection of the No. 12 EDG to be accommodated, thereby enhancing the long. term reliability of the EDG and the changes in the TS Bases are consistent with the requested changes.
- .0 STATE CONSULTATION In accordance with the Commission's regulations, the Maryland state official was notified of the proposed issuance of the amendments.
The State official had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change the surveillance requirements.
The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed fir. ding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (56 FR 46450). Accordingly, the amendments meet the eligibility criteria for ca'egorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be orepared in connection with the issuance of the amendments.
5-
7.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
R. Jenkins C. Morris Date: October 21, 1991 i
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Mr. G. C. Creel 2
(L't oler 21, 1991 A copy of the related Safety Evaluation is enclosed.
A Notice of issuance will be included in the Connission's next regular biweekly Federal Rejister notice.
Sincerely, original =1gned by:
4 Daniel G. Mcdonald, Senior Project Mana9ar Project Directorate 1 1 l
Division of Reactor Projects. 1/11 Office of Nuclear Reactor Regulation t.
Enclosures:
1.
Amendment No.163 to DPR-53 2.
Amendment No.143 to DPR.69 3.
Safety Evaluation cc w/ enclosures:
See next page DISTRIBUTION:
See attached sheet i 7V
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DATED: Detober 21, 1991 AMENDMENT NO.163 TO FACILITY OPERATING LICENSE NO. DPR-53-CALVERT CLIFFS UNIT 1 AMENDMENT NO.143 TO FACILITY OPERATING LICENSE NO. DPR-69-CALVERT CLIFFS UNIT 2 Docket file NRC & Local PDRs PDI-l Reading S. Varga, 14/E/4 J. Calvo, 14/A/4 R. Capra C. Vogan D. Mcdonald C. Cowgill F. Rosa OGC-WF D. Hagan, 3302 MNBB C. Liang 8/E/23 G. Hill [8), P-137 Wanda Jones, P 130A C. Grimes ACRS(10),11/f/23 GPA/PA OC/LFMB C. Morris R. Jenkins Plant File cc:
Plant Service list I
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