ML19338D633
| ML19338D633 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 09/16/1980 |
| From: | Novarro J COMMONWEALTH EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0696, RTR-NUREG-696 SNRC-506, NUDOCS 8009230590 | |
| Download: ML19338D633 (3) | |
Text
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LONG ISLAND LIGHTING COMPANY
[kN SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792 e
September 16, 1980 SNRC-506 Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Wcshington, D. C.
20555 Technical Support Center Shoreham Nuclear Power Station - Unit 1 Docket No. 50 122
Dear Mr. Denton:
Please refer to our letter, CNRC-486 dated July 21, 1980, that submitted the " Design Criteria ar.d Description, Technical Support
~
Center (TSC) for the Shoreham Nuclear Power Station."
In light of the coincidental development of NUREG-0696, the purpose of this letter is to:
1.
emphasize the importance and necessity of receiving your evaluation of the design criteria document as early in September 1980 as possible in order to permit development of the TSC to support our May 31, 1982 fuel load schedule; and 2.
to comment on NUREG-0696 in relation to the Shoreham
. design document.
A copy of this letter is being sent to Mr.
S. L. Ramos as requested by the August 1, 1980 letter from Mr. Eisenhut.
The NUREG-0696 draft includes four requirements which could have a major impact on the conceptua.1 design of the Shoreham TSC.
They are:
1.
Proximity to Control Room NUREG-0696 states that "the TSC shall normally be in a location that is within approximately two minutes comfortable walking time of the Control Roc.n. " Pg. 10.
The estimated comfortable walking time fro'a the proposed TSC to the Control Room is three minutes.
The route hDOI 3
I 1/b FC 4935 8009230670 4
Mr. Harold R. Denton September 16, 1980 Re:
Technical Support Center Page 2 to the Control Room from the Security Building is out of doors for approximately 190 feet, then through the Office and Service Building to the Control Building and into the Control Room; a total distance of approximately 425 feet horizontally, and 3 floor levels vertically.
The estimated walking time includes the time to pass through three security card-reader stations.
Utiliza-tion of the existing Security Building is a significant factor in the implementation of the TSC in light of our construction and fuel load schedule.
We believe that the proposed location is satisfactory and request your concurrence.
2.
Data Processing The current draft of NUREG-0696 requires that "These (instrumeatation) signals shall be transmitted, processed and displayed independently of any equipment used for normal plant operations, such as the process computer."
Pgs. 4 and 5.
We recognize that it is not practical to provide all the data processing required for the Technical Support Center, the Emergency Operations Facilities, the Safety Parameter Display System, and Nuclear Data Link, solely from the present plant process computer.
Therefore, we intend to modify our conceptual design and develop a Data Processing System to address the scope of NUREG-0696.
3.
Regulatory Guide 1.97 Data Set The current draft of NUREG-0696 requires that "The Type A, B, C, D, and E variables specified by R.
G.
1.97 form the minimum data set to be used by the Emergency Response Facilities." Pg. 4.
Implementation of this requirement for the Emergency Response Facilities will have a major impact on the completion of Shoreham.
We have previously provided an assessment of the impact of R.
G. 1.97 in our letter SNRC-460 dated January 30, 1980.
The present implementation date of the Regulatory Guide, June 1983, would require installation to be performed coincident with preoperational testing.
This is particularly unsettling because of the indefinite nature of R.
G. 1.97, in light of the August 6 ACRS meeting.
Furthermore, it is our understanding that the next issue of R.
G. 1.97 will not be available until November 1980.
s Mr. Harold R. Denton September 16, 1980 Re:
Technical Support Center Page 3 Based on these circumstances, and for the reasons stated in SNRC-460, we believe that the data set included in the Shoreham design document is adequate for a TSC.
The need for additional variables should be established in conjunction with the NRC's evolving definition of the instrumentation required for the safety parameter display system.
4.
Safety Parameter Display System (SPDS) r sign Criteria e
The requirement that, "The SPDS shall be capable of functioning during and following events expected to occur during the life of the plant, including the operating basis earthquake," pg.
2, is an unrealistic restraint.
It eliminates the option of using existing plant computers, while simultaneously ignoring the fact that seismically qualified computers for power plant applications are not available.
We request your evaluation and support of our efforts to implement a meaningful TSC at Shoreham.
Furthermore, since the completion of the TSC is a critical item on the Shoreham construction schedule, we request that you advise us as early in September 1983 as possible of the acceptability of the TSC as described in the Shoreham design basis document.
Very truly yours,
.ic J.
P. Novarro, Project Manager Shoreham Nuclear Power Station RAH /cc c :
J.
Higgins i-1
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