ML20058L785

Application for Amends to Licenses DPR-53 & DPR-69,revising 870710 Tech Spec Amend Request Re Reactor Vessel Level Monitoring Sys Action Statement 35-3 in Table 3.3-10

ML20058L785
Person / Time
Site:	Calvert Cliffs
Issue date:	08/03/1990
From:	Creel G BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20058L788	List: ML20058L785 ML20058L789
References
TAC-67954, TAC-67955, NUDOCS 9008080106
Download: ML20058L785 (3)

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CHARLES CENTER e P.O. BOX 1475 e BALTIMOR: MARYLAND 21203 1475 Geomot C. CRctL Vate Pas sacch, g Nucitan rhtmov boooooass6 August 3,1990 l U. S. Nuclear Regulatory CommisOn Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & $0-318 Revision to Amendment Request on Reactor Vessel Level Monitoring System (TACs 67954 and 67955) and Supplemental Information on Core Exit Thermocouples f

REFERENCES:

(a) Letter from Mr. J. A. Tiernan (BG&E) to NRC Document Control

[ Desk, dated July _10,1987,_ Request for Amendment ,

(b) Letter from Mr. D. M. Crutchfield (NRC) to Mr. R. W. Wells (CE), dated October 28, 1986, . Reactor Vessel Level Monitoring C

System Technical Specification Safety Evaluation (c) Letter from Mr. J. A. Tiernan (BG&E) to NRC Document Control i Desk, da" ' ,e 16,1988, Request for Amendment (d) Letter from Mr. G. C. Creel (BG&T.; ?.o NRC Document Gntrol Desk, dated September 20, 1989, Response to Request for Adrenst l Information Regarding Core Exit Thermecouples E Gentlemen:

l In accordance with previous discussions with your staff, we request a revision to our

_ Technical Specification Amendment Request contained in Reference (a). This revision is '

to the Reactor Vessel Level Monitoring System (RVLMS) ACTION STATEMENT 35-3 contained in Table 3.3-10 " Post Accident Monitoring instrumentation." We have '

changed the sentence:

' Restore at least one channel to OPERABLE status at the next refueling? ,

I to

' Restore the system to OPERABLE status at the next refueling," 3 I (

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Document Contr;l Desk

. August 3,1990

.. Page 2 This revision is more restrictive than our previous submittal by requiring both channels to be operable rather than just one and it conforms to the guidance contained in Reference (b). Because the revision is more testrictive than our previous submittal, our significant hazards determination contained in Reference (a) will not change. The only changes necessary are contained in Attachment (1). All other pages from our previous submittal remain the same.

You have also verbally requested that a more detailed core map be supplied for our Core Exit Thermocouple (CET) amendment request and supplemental information contained in References (c) and (d), respectively. The two areas of concern are:

1. loss of a single power supply will not result in a loss of all CETs in a -

core quadrant; and I

2. the remaining operable CETs in a quadrant provides at least one CET near the center of the core and one near the perimeter.

In response to this request, the Calvert Cliffs Units I and 2 core quadrant maps attached to Reference (d) have been annotated to identify the CET power supplies as channel "ZA' or 'Z B", and are provided as Attachment (2). Also as identified in Reference (d), the Unit 2 CETs are now qualified except for the four locations, 34, 38, 41 and 45; one in each quadrant. Therefore Unit 2 easily satisfies both of the above criteria. In Unit 1, 23 of 45 CETs have been replaced with qualified CETs to date. These CETs are distributed such that the first criteria identified above is met. At this time, there is a single exception to the second criteria: the quadrant which contains CET Nos. 2, 10, 13, 14, 15, 16, 17, 33, 34, 35 and 36. Of these, 10,  ;

14, 33, 34 and 35 are qualified, but only 14 is 'ZB" powered. Therefore, this quadrant '

of Unit I does not provide for mrasuring radial enthalpy gradient using the "ZB" channel. The remaining Unit 1 CETs are scheduled to be replaced in upcoming outages and the second criteria identified above will eventually be met.

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' August 3,1990 '

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I Should you have any questions regarding these matters, we will be pleased to discussed 1 them with you.  ;

i Very truly you

/ 1 STATE OF MARYLAND  :

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I hereb cer fy that on the d/Ub day of /44045 , 19 1, before me, the sppseribesa Notary Public of the State of Maryland in and for s httrt

('f//aTr t- , personally appeared George C. Creel, being duly sworn, and states ihat he il 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 therein 1 set forth; that- the statements made are true and correct to the best of his knowledge, L information, and belief; and that he was authorized to provide the response on behalf -

s f said Corporation.

WITNESS my lland and Notarial Scal: 874 -

Notary Public o //I4(/

j My' Commission Expires: W/uAs t, /, /I9M U- Qate ' .

GCC/DBO/ dim l Attachments: (1) Proposed Technical Specification Changes (4 pages)

(2) CET Maps (2 pages) l< cc: D. A. Brune, Esquire 1 E. Silberg, Esquire A. A.Capra, NRC D. G. Mcdonald, Jr., NRC T, T. Martin, NRC

!.. E. Nicholson, NRC R.1. McLean, DNR w