ML20072T820

Application for Amend to Licenses DPR-53 & DPR-69 Replacing Tech Spec Page 3/4 6-26 Re Containment Sys & Deleting Setpoint & Allowable Values from Loss of Turbine Portion of Reactor Protection Sys Table 2.2-1

ML20072T820
Person / Time
Site:	Calvert Cliffs
Issue date:	03/22/1983
From:	Lundvall A BALTIMORE GAS & ELECTRIC CO.
To:	Clark R Office of Nuclear Reactor Regulation
Shared Package
ML20072T823	List: ML20072T820 ML20072T828
References
NUDOCS 8304080341
Download: ML20072T820 (3)

Text

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d' ' .. BALTIMORE GAS AND 4.-

1 E'LECTRIC

' CHARLES CENTER P.O. BOX 1476 BALTIMORE, MARYLAND 21203 March 22,1983

. , ARTHUR L LUNOVALL, JR.

' Vier PRES 4 DENT SUPPLY

10. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 ATTENTION: Mr. Robert A. Clark, Chief 4 5 Operating Reactors Branch #3 Division of Licensing -

SUBJECT:

Calvert Cliffs Nuclear Power Plant -

, Unit Nos.~ l & 2; Docket Nos. 50-317 & 50-318 Request for Amendment Gentlemen:

Baltimore Gas and Electric Company hereby requests an Amendment for Operating

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Licenses DPR-53 and DPR-69 for Calvert Cliffs Unit Nos.1 & 2, respectively, with the ' >

submittal of the enclosed proposed changes to the Technical Specifications.

CHANGE NO.1 (BG&E FCR 83-29)

Remove existing pages 3/4' 6-26.of Unit Nos. I and 2 Technical Specifications, and replace with attached, marked up pages 3/4 6-26.

DISCUSSION AND JUSTIFICATION

-The solenoid valves for one H 2 Analyzer are not environmentally quallfled.

Environmentally quallfled valves were not available when modifications related to TMI

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Action item II.F.1.6 of NUREG-0737 were completed in late 1982. As described in the October 23, 1981, letter to D. G. Eisenhut from' A. E. Lundvall, Jr., the environmental qualification issue is being handled separately from the TM1 modification.

i Relaxation of the Action Statement for 3.6.5.1 for a 60 day period should allow sufficient time for installation and testing of the new environmentally qualified valves in the H2 Analyzer. During the replacement of the valves, the modification will be controlled such

' that no' more than one H2 Analyzer is rendered inoperable at a time. _During the time one-H2Analyzer is inoperable, if the second analyzer is needed for . operation (e.g.,

followmg a loss' of coolant accident or to sample the rad waste tanks), replacement of key components in the second analyzer can be carried out in a reasonable length of time, should the need arise. If the only operable H2 Analyzer should fail, the design function f can 'be ; accomplished by a grab sample or by substituting the pump from the other pD

, . Analyzer.' A single H 2; Analyzer can sample either containment atmosphere.'

We are also requesting relaxation of Technical Specification 3.0.4'during this period, such

. _ that we will be allowed to change operational modes with one hydrogen analyzer;

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Mr. R. A. Clark March 22,1983

Page 2 t

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Inoperable, as long as the other channel remains operational.

5 7 CHANGE NO. 2 (BG&E FCR 83-02) 7 A. Delete setpoint and allowable values from the loss of turbine portion of the Reactor Protective System (RPS) Table 2.2-1 of the Technical Specifications; replace old E Table 2.2-1 with new Table 2.2-1 as shown on attached marked-up copies.

[ (Attachments la and Ib).

B. Change the designation of loss of turbine trip to " loss of load" on RPS Table 2.2-1, 3.3-1, 3.3-2, 4.3-1 and page B2-7 of the Technical Specification Bases; replace old

, tables and page B2-7 with new tables and pages as shown on attached marked-up

[ copies (Attachments la, Ib, 2a, 2b, 3a, 3b, 4a, 4b, Sa, 5b, 6a, 6b).

C. Modify last sentence of " loss of turbine" paragraph, page B2-7 of the Technical Specification Bases to more accurately reflect the actual purpose and requirement for functional capability of the trip. Replace old page B2-7 with new page B2-7 as g shown on attached marked-up copies (Attachment Sa,5b).

$ DISCUSSION AND 3USTIFICATION

[ The loss of load reactor trip for Units 1 and 2 is presently listed in Tables 2.2-1, 3.3-1,

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3.3-2 and 4.3-1 of the Technical Specifications as a " loss of turbine - - hydraulic fluid pressure-low", with listed trip setpoints and allowable values of " >_1100 PSIG". The trip is also described in the bases section (page B2-7) of the Technical Specifications as a

" loss of turbine" trip. These designations are incorrect in that the trip should actually be

( designated " loss of load", as labeled on the reactor protective system and as described in

the Updated Final Safety Analysis Report.

$ The Unit I trip function does not occur as a result of low turbine hydraulic fluid pressure, e-but by the action of external trip contacts off of the main turbine master trip solenoid circuit. The Unit 2 trip function does not occur specifically as a result of low hydraulic k: ,

fluid pressure, but rather, as a function of auto stop oil pressure sensed by four separate pressure switches. These pressure switches operate on 50 PSIG decreasing pressure to h.

r provide trip signals to the auxiliary trip unit in the reactor protective system. The trip y

function is provided as an equipment protective feature which reduces the number of r

challenges to overpressure protective devices in the primary and secondary systems. The loss of load trip is not considered or given credit in the accidents described in Chapter 14 L' the Updated Final Safety Analysis Report.

[ The presently approved surveillance test procedure used to ensure operability of the loss y of load reactor trip satisfactorily checks its functional capability. Operability of the Unit 2 pressure switches is checked under the preventive maintenance system. Setpoint x-and allowable values for this functional trip are therefore not applicable, and their

, deletion from Table 2.2-1 reflect this fact. The final sentence of the " loss of turbine" paragraph on page B2-7 of the Technical Specification Bases has been revised to more accurately reflect the intended purpose and functional nature of this equipment

> protective trip.

r Mr. R. A. Clark March 22,1983 Page 3 Because this trip is not considered safety related, and because the proposed changes provide clarification and correct errors in the Technical Specifications and their bases, they do not constitute an unreviewed safety question. There is no reduction in the margin of safety used in the bases for the Technical Specifications or. In the Updated Final Safety Analysis Report, and no increased risk to the health and safety of the public.

SAFETY COMMITTEE REVIEW This proposed change to the Technical Specifications has been reviewed by our Plant Operations and Safety and Off-Site Safety Review Committees, and they have concluded that implementation of this change will not result in an undue risk to the health and safety of the public.

FEE DETERMINATION Based on discussions with Mr. D. H. Jaffe, Project Manager, NRC, we understand the fee for this Amendment will be covered under the submittal dated February 24,1983.

BALTIMORE GAS AND ELECTRIC COMPANY

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By: , l. 4 a A>/

Wice Presidenfa Supply /

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AEL/LES/ JET /sjb STATE OF MARYLAND  :

TO WIT:

CITY OF BALTIMORE  :

Arthur E. Lundvall, Jr., being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therar forth; that the statements made are true and correct to the best of his knowledge, 9 wation, and lief; and that he was authorized to provide the response on behalf of corpora i .

WITNESS my Hand and Notarial Seal: A1/-/ . /e " ~

/ou Kofdff Public/

My Commission Expires: 7r dA / / ,/Mb cc: 3. A. Biddison, Esquire G. F. Trowbridge, Esquire D. H. 3affe, NRC R. E. Archltzel, NRC

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