ML20155J915

Forwards Response to NRC 980902 RAI Re Review of CCNPP Integrated Assessment Rept for Safety Injection Sys,Per License Renewal

ML20155J915
Person / Time
Site:	Calvert Cliffs
Issue date:	11/09/1998
From:	Cruse C BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9811130036
Download: ML20155J915 (4)

Text

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CHAILEs H. C USE Baltimore Gas and Electric Company Vice President Calvert Cliffs Nuclear Power Plant

. Nuclear Energy 1650 Calven Cliffs Parkway Lusby, Maryland 20657 410 495-4455 November 9,1998 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Responses to Requests for Additional Information for the Review of the Calvert Cliffs Nuclear Power Plant, Units 1 & 2, Integrated Plant Assessment Report for the safety injection system

REFERENCES:

(a)

Letter from Mr. C. H. Cruse (BGE) to NRC Document Control Desk, dated March 3,1998," Request for Review and Approval of System and Commodity Reports for License Renewal" (b)

Letter from Mr. D. L. Solorio (NRC) to Mr. C. H. Cruse (BGE),

September 2,1998," Request for Additional Information for the Review

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of the Calvert Cliffs Nuclear Power Plant, Units 1 & 2, Integrated Plant Assessment Report for the Safety Injection System"

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Reference (a) forwarded five Baltimore Gas and Electric Company (BGE) system and commodity reports for license renewal. Reference (b) forwarded questions from NRC staff on one of those five

[3g, reports, the Integrated Plant Assessment Report for the Safety Injection System. Attachment (1) provides our responses to the questions contained in Reference (b).

9811130036 981109. rK PDR ADOCK 05000317 I

P PDR y

NRC Distribution Code A0360

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Document Control Desk Novrmber 9,1998 Page 2 Should you have further questions regarding this matter, we will be pleased to discuss them with you.

Very truly yours, STATE OF MARYLAND

TO WIT:

COUNTY OF CALVERT I, Charles H. Cruse, being duly sworn, state that I am Vice President, Nuclear Energy Division, Baltimore Gas and Electric Company (BGE), and that I am duly authorized to execute and file this response on behalf of BGE. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other BGE employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

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Su)A(jbed and sworn beforeye a Notaryjublic in pnd for the State of Maryland scr f

(

DfAf)

, this 7tA; day of R/M ntLfA/1998, i

PA11a) b 2 4t1L A_L/

WITNESS my Hand and Notarial Seal:

Notary Public My Commission Expires:

b

'l M3 Date CHC/DLS/ dim

Attachment:

(1) Response to Request for Additional Information; Integrated Plant Assessment

. Report for the Safety Injection System cc:

R. S. Fleishman, Esquire C. I. Grimes, NRC J. E. Silberg, Esquire D. L. Solorio, NRC S. S. Bajwa, NRC Resident Inspector, NRC A. W. Dromerick, NRC R. I. McLean, DNR H. J. Miller, NRC J. H. Walter, PSC

~.

i.

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ATTACHMENT (1) 1 1

i RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; INTEGRATED PLANT ASSESSMENT REPORT FOR TIIE SAFETY INJECTION SYSTEM Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant November 9,1998

ATTACHMENT (1)

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RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION; INTEGRATED PLANT ASSESSMENT REPORT FOR THESAFETYINJECTION SYSTEM l

NRC Ouestion No.1 10 CFR 54.21(a)(1) states that valve bodies are passive. Page 5.15-12 (ofBaltimore Gas and Electric l

Company's [BGE's] License Renewal Application [LRA]) identifies 29 device types as having only l

active functions, solenoid valves being one of these 29 components. The drawing on pages 5.15.6 and i

5.15.7 show solenoid valve bodies being within the evaluation boundary. Provide a justificatian fer not l

including the pressure boundary function of solenoid valve bodies as being within the scope of the aging management review (AMR).

BGE Response

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Contrary to the statement above, the drawings on pages 5.15.6 and 5.15.7 do not show any solenoid j

. valve bodies within the evaluation boundary. The key provided with the drawings shows the components are flow orifices, control valves, hand valves, check valves, motor-operated valves, relief valves, and spoci pieces. The air provided to control valve operating schemes in the Safety Injection System is non-safety-related; therefore, solenoid valves do not provide the pressure boundary function. Page 5.15-12 is, therefore, correct in identifying solenoid valves as being one of the 29 components having only active functions.

j NRC Question No. 2

- Page 6.3-3 (Revision 18) of the Calvert Cliffs Nuclear Power Plant Updated Final Safety Analysis Report l

indicates that there is a small drain valve controlled remotely from the Control Room, which is intended i

to drain any leakage from the Reactor Coolant System into the Safety Injection System. Was this drain valve subjected to an AMR7 If so, provide a cross reference to where this is addressed in the LRA. If not, provide the basis for exclusion.

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l BGE Response The drain valves described above are associated with the safety injection tanks (SITS). The valves are l

pneumatically-operated Control Valves 1(2)CV611,1(2)CV621,1(2)CV631, and 1(2)CV641. These valves are opened to allow draining Reactor Coolant System in-leakage to the SITS and are represented on Figure 5.15-1 immediately to the left of the SIT. These valves were subjected to an AMR, and are considered in the Safety Injection portion of the LRA (Section 5.15, " Safety Injection System") as control valves.

l l-NRC Ouestion No. 3 Page 6.3-14 (Revision 21) of the Calvert Cliffs Nuclear Power Plant Updated Final Safety Analysis l

Report indicates that the containment sump suctions are enclosed by particulate screens. Are these screens included within the AMR7 If so, provide a cross reference to where they are addressed in the LRA. If not, provide the basis foi exclusion.

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BGE Response The containment sump particulate screens are considered in LRA Section 3.3A, " Primary l:-

Containment Structure." They are specifically identified on page 3.3A-6 under Unique Components.

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