ML19256F310
| ML19256F310 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/10/1979 |
| From: | Counsil W, Willie Lee CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912180478 | |
| Download: ML19256F310 (2) | |
Text
i CONNECTICUT YA N K EE AT O M IC POWER COMPANY BERLIN, CONNECTICUT P.O. BOX 270 H A RTFOR D. CON N ECTICUT 06101 TELuewows 203-666-6911 Dec ember 10, 1979 Docket No. 50-213 Director of Nuclear Reactor Regulation Attn:
Mr. D. L. Ziemann, Chief Operating Reactors Branch #2 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Reference:
(1)
D. L. Ziemann letter to W. G. Counsil dated November 5,1979.
Gentlemen:
Haddam Neck Plant Control Rod Position Indication In Reference (1), Connecticut Yankee Atomic Power Company (CYAPCO) was requested to sdpply information with regard to the Control Rod Position Indication System and rod misalignment, and to ensure that the control rods are required to be maintained within saf ety analysis assumptions.
In accordance with the current requirements of DPR-61, the Technical Specifica-tions for the Haddam Neck Plant do not specify acceptable limits for control rod misalignment.
It must also be noted that the configuration of the plant is such that a direct comparison with the specific examples of Reference (1) is not appropriate.
For example, the coils on the control rods which generate the signal for the analog rod position indication system are continuous coils 132" in length at the Haddam Neck Plant, as opposed to multiple coils as in Reference (1). Misalignment is limited by the fact that control rod positions are continuously monitored by the plant's process computer and an alarm is initiated if any rod in a bank is more than 16 steps out (6") from the bank average position.
Operators are then procedurally required to bring that rod back into position.
With the computer out of service, operators are procedurally required to check relative rod positions hourly.
It is also relevant that the current fuel and safety analysis vendor is Babcock & Wilcox.
These and other plant-unique features require additional investigation to determine the extent of their effect on this issue.
CYAPC0 acknowledges the Staff's concern on this matter and is proceeding with this investigation with the intent of responding by January 31, 1980.
1609 063 7912180 & 7 F
i
' We trust you will concur that this slight delay is justified in light of the significant effort associated with our implementation of the TMI-related short-term lessons learned.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY W. G. founsil Vice President By:
W. F. Fee Vice President 1609 064