ML20087H914

Application for Emergency Amend to License DPR-53.Amend Would Revise CREVS TSs to Provide an Extension of Allowed Outage Time

ML20087H914
Person / Time
Site:	Calvert Cliffs
Issue date:	04/28/1995
From:	Denton R BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20087H918	List: ML20087H914 ML20087H928
References
NUDOCS 9505050117
Download: ML20087H914 (6)

Text

1 RostaT E. DENTON Baltimore Gas and Electric Company Vice President Calvert Oiffs Nuclear Power Plant Nuclear Energy 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410 586-2200 Ext.4455 local 410 260-4455 Baltimore April 281995 U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Cakert Cliffs Nuclear Power Plant Unit No.1; Docket No. 50-317 Emergency License Amendment Request; Unit 1 Control Room Emergency Ventilation System Technical Specification Extension

REFERENCES:

(a) Letter from Mr. R. E. Denton (BGE) to NRC Document Control Desk, dated September 23, 1994, License Arr.endment Request; One-Time Technical Specification Changes to Support the 1995 Refueling Outage (b) Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE),

dated January 11, 1995, Issuance of Amendments for Calvert Cliffs Nuclear Power Plant, Unit No.1 (TAC No. M90500) and Unit No. 2 l (TAC No. M90501)

Pursuant to 10 CFR 50.90, the Baltimore Gas and Electric Company hereby requests an Emergency l

Amendment to Operating License No. DPR-53 by incorporating the changes described below into the Technical Specifications for Calvert Cliffs Unit 1.

l DESCRIPTION ne proposed emergency amendment would revise the Unit 1 Control Room Emergency Ventilation System (CREVS) Technical Specifications to provide an extension from 30 to 45 days of the allowed outage time for one train hoperable due to the emergency power supply being inoperable. His is an extension of the previously requested and approved change (References a and b).

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BACKGROUND I Currently, Calvert Cliffs Nuclear Power Plant uses three emergency diesel generators (EDGs) to provide the emergency onsite power supply. Normally, No.11 EDG is dedicated to Unit 1, No. 21 EDG is dedicated to Unit 2, and No.12 EDG is the " swing" EDG and is capable of powering one emergency bus on either unit. Offsite AC electrical power is provided by three independent 500 kV transmission lines.

Ecse lines provide offsite power to the units during normal operations as well as during startup and shutdown. He system is also designed with the capability for a single 500 kV line to power both units l

simultaneously. This diversity ensures that the loss of two 500 kV lines will not result in a loss-of-offsite power. In addition to the three 500 kV transmission lines, there is a 69 kV line from Southem Maryland Electric Cooperative. This line is capable of supplying the power for all required safe shutdown loads for both units as described in Updated Final Safety Analysis Report Section 8.2.4.  !

Calvert Cliffs has a common Control Room for the two units and the CREVS consists of two redundant trains. The CREVS is designed so that the Control Room can be occupied under all plant conditions.

Number 11 CREVS receives power from Unit I through 4 kV Bus No. I1 with No.1I EDG as the emergency power supply, and No.12 CREVS receives power from Unit 2 through 4 kV Bus No. 24 with No. 21 EDG as the emergency power supply. With either unit in Modes I through 4, the Technical Specifications require both trains of the CREVS to be operable.

As described in Reference (a), No. 21 EDG was scheduled to be upgraded during the 1995 Unit 2 Refueling Outage. He upgrade modification is being done to increase the electrical capacity of the existing EDGs to provide additional margin for the electrical loading of the 4 kV safety-related busses, thereby improving the margin of safety for the onsite electrical distribution system. The upgrade on No. 21 EDG resulted in No.12 CREVS not having a safety-related emergency power supply during the upgrade. This required Baltimore Gas and Electric Company to request a one-time Technical Specification change to the Unit 1 CREVS (Reference a). This request was approved in Reference (b). The No. 21 EDG upgradv Was expected to be completed within 30 days. On April 3,1995, No. 21 EDG was taken out-of-senice to begin the upgrade modifications. Modifications were completed on April 13, 1995, with testing starting on April 14. During testing, multiple problems were discovered that resulted in several test iterations. As of April 26, Number 10 cylinder was still experiencing low firing pressure and high exhaust temperature.

Several corrective actions suggested by the vendor have been tried but have not corrected the problems. An engine analysis contractor was on site by April 27 to troubleshoot these problems. Troubleshooting is expected to be complete within a week. The necessary testing to restore No. 21 EDG as an emergency power supply for No.12 CREVS should be completed within the following four days. Ilowever, the Unit 1 CREVS Action Statement will expire on May 3, requiring Unit I to be shut down. The upgrade modification is similar to modifications completed on No.1I EDG during the 1994 Unit 1 Refueling Outage, and to those done elsewhere in the industry. We did not experience these problems during the No. I1 EDG upgrade and, therefore, did not foresce them on No. 21 EDG. As a consequence, the necessity for this emergency relief could not have been reasonably avoided.

4 During the period the No. 21 EDG is out-of-senice, planned maintenance will be prohibited on three of the l four offsite power sources. In addition, a temporary diesel generator will be connected to 4 kV Bus No. 24 i to provide assurance that AC power would be available to No.12 CREVS. These are the same I compensatory measures approved for the 30-day allowed outage time extension (Reference b). There is no other Technical Specification that is affected by this extension. Number 11 EDG will be aligned to l

Document Control Desk April 28,1995 Page 3 4 kV Bus No. I1 and No.12 EDG will be available as the " swing" diesel generator for Unit I to 4 kV Bus No.14, or for Unit 2 to 4 kV Bus No. 21. Therefore, Unit I will have the two required safety-related EDGs to support power operation, and Unit 2 will have the one required safety-related EDG to support safe shutdown conditions. Without an extension of the Unit 1 CREVS Technical Specification 30-day allowed outage time for emergency power to 45 days, Unit I will be required to shutdown on May 3,1995.

REOUESTED CIIANGE Change Specification 3.7.6.1 of the Unit 1 Technical Specifications as shown on the marked-up page attached to this transmittal.

SAFETY ANALYSIS During the time No. 21 EDG is out-of-service, the loss of Control Room habitability is the concern. The CREVS is required to maintain the Contiol Room temperature below a specified limit and to filter the Control Room air in the event of a radioactive release. He probability of a loss of both trains of CREVS is very low. Number 11 CREVS will have both its normal power source and its emergency power source available during this period. Number 12 CREVS will also have its nonnal power source available.

Number 12 CREVS will not have a safety-related emergency power supply, but will have the temporary diesel generator available. Loss of all power to both trains of the CREVS would require a loss-of-offsite power, the failure of No. I1 EDG to start, and the failure of the temporary diesel generate to start. This sequence of events is highly unlikely.

DETERMINATION OF SIGNIFICANT IIAZARDS The proposed change has been evaluated against the standards in 10 CFR 30.92 and has 1.cen determined to not involve a significant hazards consideration, in that operation of the facility in accordance with the proposed amendments:

1. Would not imvive a sigmficant increase in the probability or consequences of an accident previously evaluated.

Mc Control Room Emergency Ventilation System (CREVS) is designed so that the Control Room can be occupied under all plant conditions. He CREVS is required to maintain the Control Room temperature and to filter the Control Room air in the event of a radioactive release. During the ,

time No. 21 Emergency Diesel Generator is out-of-service, No.12 CREVS will be without a l Class IE emergency power source. He CREVS is not an initiator in any previously evaluated I accidents. Therefore, the proposed change does not involve an increase in the probability of an )

accident previously evaluated.

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He CREVS is required to maintain the Control Room habitable following a radioactive release I from a loss-of-coolant accident, a main steam line break, or a steam generator tube rupture. There l is a very low probability of an event occurring requiring Control Room isolation during the {

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extended penod Requiring that the CREVS have both a nonnal power source and an s.,,..::y power source available ensures that one train of the system will be available so that the Control Room can be occupied under these conditions. De probability of a loss-of-ofsite power is very.

Iow due to the highly mdundant design of the ossite power supply. Planned manuenance on three of the ossite power supplies and associated relaying and devices within the switchyards will be prohibited during the extended period to maintam the low probability of a loss-of-offsite power event. Number 12 CREVS train will continue to have its' normal power source. Number 11.

CREVE will have both its normal and emergency power supply available and this train is capable of C= ' ; the Control Room habitable. In d Wa. a i ..preiy diesel generator is installed to provide assurance that an emergency power source will be available to No.12 CREVS. %c compensatory measures that will be taken during this period will ensure that the proposed change does not involve a significant increase in the consequences of an accident previously evaluated.

Derefore, 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 nm or diferent type of accident from any accident previously enluated.

The CREVS is not being modified by this proposed change. The system will continue to operate in the same manner. Number 21 Emergency Diesel Generator will operate in a similar manner after it is mturned to service and will be able to support unit operaten after all the testmg is completed.

De installation of the temporay diesel generator during the extended period has been evaluated to ensure that is does not create any new accident initiators. Derefore, 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 ofsafety.

He operability of the CREVS during Modes 1 through 4 ensures that the Control Room will remain habitable under all plant conditions. De proposed change does not affect the function of the CREVS. De proposed change will allow one train of the CREVS to be without a Class IE emergency power supply for up to a total of 45 days. His train will have the normal power supply available. De other train of the CREVS will have both its normal and emergency power supplies during this period. Compensatory measures that will be taken include prohibiting planned maintenance on the required offsite power sources, and installing a temporary diesel generator of mflicient capacity as a backup to the affected train. These measures will maintain the current margin of safety. Derefore, the proposed change does not involve a significant reduction in a margin of safety.

. . Dew Control Desk April 28,1995 Page 5 ENVIRONMENTAL ASSESSMENT The proposed amendment would change requirements with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20, or changes to an inspection or surveillance requirement. We have determined that the proposed amendment involves no significant hazards consideration, and that operation with the proposed amendment would result in no significant change in the types or significant increases in the amounts of any efYluents that may be released offsitc, a::d in no significant increase in individual or cumulative occupational radiation exposure. Therefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR Part $1.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or emironmental assessment is needed in connection with the approval of the proposed amendment.

SCHEDULE nis change is requested to be approved and issued by May 3,1995. As discussed in the BacQround Section of this letter, issuance of this amendment is identified as impacting continued plant operation.

SAFETY COMMITTEE REVIEW These proposed changes to the Technical Specifications and our determination of significant hazards have I been reviewed by our Plant Operations a.J Safety Review Committee and Offsite Safety Resiew Committee. They have concluded that implementing these changes will not result in an undue risk to the health and safety of the public.

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, . . D.:- ==? Control Desk I April 28,1995 i Page 6 Should you have questions regarding this matter, we will be pleased to discuss them with you.

. Very truly >vurs,

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i lr v i STATE OF MARYLAND -

TO WIT:

COUNTY OF CALVERT  :

I hereby certify that on the d80 day cf OU Notary Public of the State of Maryland in and f6r (#2/ ant /En,vt_

.193 before me, the subscriber, a 7

. personally appeared Robert E. Denton, being duly sworn, and states that he is Vice President 6f the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, i information, and belief; and that he was authorized to provide the response on behalf of said Corporation.

I Wili!ESS uy Hand and Notarial Seal.

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Notary Public i

My Commission Expires: dM11AA2; / , / N8 _

() (ate '

Attachment:

(1) Unit 1 Marked-Up and Final Technical Specification Page 3/4 7-16 l

i RED /DJM/ dim cc: D. A. Brune, Esquire J. E. Silberg, Esquire {

L. B. Marsh, NRC D. G. Mcdonald, Jr., NRC  ;

1 T. T. Martin, NRC -l P. R. Wilson, NRC l R. I. McLean, DNR J. H Walter, PSC i

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