ML17328B075

Safety Evaluation Supporting Amends 137 & 120 to Licenses DPR-53 & DPR-69,respectively

ML17328B075
Person / Time
Site:	Calvert Cliffs
Issue date:	05/18/1989
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML17328B074	List: ML17328B073 ML17328B075
References
NUDOCS 8905300168
Download: ML17328B075 (6)

Text

gp,R RKgy

~4 0

Cy I

0O

+a*++

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 137 TO FACILITY OPERATING LICENSE NO. DPR-53 AND AMENDMENT NO. 120 TO FACILITY OPERATING LICENSE NO. DPR-69 BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS NUCLEAR POMER PLANT UNITS I AND 2 DOCKET NOS. 50-317 AND 50-318 INTRODUCTION By the letter dated April 14, 1986, as supplemented on April 28, 1987, the Baltimore Gas and Electric Company (BGSE, the licensee) proposed to change the Units I and 2 Technical Specification (TS) 3/4.8.2.3, "Electrical Power Systems:

D.C. Distribution - Operating,"

by deleting the 18-month station battery service test's dummy load profile from TS Surveillance Requirement 4.8.2.3.2.d.2.

Instead, TS 4.8.2.3.2.d.2 shall specify that the load profile will be maintained in Chapter 8 of the Calvert Cliffs Nuclear Power Plant Units I and 2 Updated Final Safety Analysis Report (UFSAR) where it shall be controlled through the processes described in 10 CFR 50.59, "Changes, Tests and Experiments."

DISCUSSION AND EVALUATION The licensee has requested to change the controlling documentation for the station battery load profile from the TS to the UFSAR in order to readily facilitate the shifting or modification of emergency loads between the four separate station batteries when necessitated by plant modifications and hardware additions.

This change is administrative in nature.

No plant operations or equipment are immediately affected by this TS modification.

TS 4.8.2.3.2.d will still continue to require the station batteries to successfu11y undergo 18-month battery service tests under design basis emergency loading conditions.

The only effect of this change is that the actua'I design basis emergency loading conditions (or load profile) shall be specified in the UFSAR rather than the TS Surveillance Requirements.

This shall permit the licensee greater flexibilityin loading the station batteries to permit better load balancing and optimize station battery and safety system performance.

In addition, any future load profile changes must be fully defined with an adequately reviewed and approved safety evaluation completed in accordance with the provisions of 10 CFR 50.59 prior to implementation.

Finally, updating of the load profiles to reflect actual plant conditions could be performed on a real time basis 8905300i68 8905i8 PDR ADOCK 050003i7 P

PDC

~

4

~,

4rr

~

~ ~

4 r

r rr ~

4

~ ~

4 i"

~ 4

~ I

~

~

\\ ~

4 I

4 4

4'

~

~ 4

~"

4

~'

4 4

'4,

~

~

4'

instead of being subjected to the time delays inherent in the TS amendment process

( i.e., 30-day pre-notice).

Consequently, the NRC staff has determined that the deletion of the dueqy load profile from TS 4.8.2.3.2.d, with the accompanying addition of a reference to the load profile contained in Chapter 8 of the UFSAR, is acceptable.

Currently, the licensee is performing a

new station battery load study.

The current requirements of TS 4.8.2.3.2.d shall remain in.effect until 14 days, after the licensee issues a notarized letter to the Commission providing official certification of the completion, approval and implementation, in accordance with the provisions of 10 CFR 50.59, of the station battery new design load study reflecting current plant conditions at Calvert Cliffs.

INTENT The intent of the proposed change is to remove the station battery service test load profile from the Technical Specifications and to relocate this load profile in Chapter 8 of the UFSAR where it shall be controlled in accordance

.with the processes provided in 10 CFR 50.59.

Load profile changes will be permitted only after the completion and approval of a 10 CFR 50.59 safety evaluation.

ENVIRONMENTAL CONS IOERATION These amendments involve a change to a surevillance requirement.

The staff has determined that these 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 Corrmission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding.

Accordingly, these amendments meet the e'ligibility criteria for categorical exclusion set forth in 10 CFR Sec 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance nf these amendments.

CONCLUSION The Commission made a proposed determination that these amendments involve no significant hazards consideration, which was published in the Federal Re ister (53 FR 40982) on October 18, 1988.

The Commission consulted witt ttte tate o

Maryland.

No public comments were received and the State of Maryland agreed with the issuance of the amendment.

'<< I

~

~

~ >> ~

~

~ g

~ ~

I

~ ~

<<A 1

I I

.<<I T<<

~

<<<<, >>')

~

~

'>>\\

~

~ >>

~ >

I

~ I I

/ )

~

~ ~

i4 l

~ j

>>m>>

Based on the considerations discussed above, that:

(I) there is reasonable assurance that'the health and safety of the public will not be endangered by operation in the proposed

manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Dated:

May 18, 1989 PRINCIPAL CONTRIBUTORS:

. S.A. McNeil C.E. Morris

~

~

~

ll

~ ~

~

~

~

~ l

~

5 -}

~

r

~ \\i l

"5

)~

I 5

~ (~55 '

i ~ 'l)

I

~

P