ML20235P205
| ML20235P205 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 10/01/1987 |
| From: | Papanic G YANKEE ATOMIC ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20235P208 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 87-107, NUDOCS 8710070208 | |
| Download: ML20235P205 (2) | |
Text
-
]
l Telephone (617) 8724100 TWX 710-380-7619 YANKEE ATOMIC ELECTRIC COMPANY y
1671 Worcester Road, Framingham, Massachusetts 01701 October 1, 1987 FYR No.87-107 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention:
Mr. Morton B. Fairtile Project Directorate I-3 Division of Reactor Projects I-II
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) YAEC Letter to USNRC, dated August 30, 1983 (FYR 83-81)
(c) YAEC Letter to USNRC, dated January 19, 1984 (FYR 84-08)
(d) YAEC-Letter to USNRC, dated July 16, 1984 (FYR 84-77)
(e) USNRC Letter to YAEC, dated August 6, 1985 (NYR 85-134)
(f)' YAEC Letter to USNRC, dated October 22, 1985 (FYR 85-113)
(g) USNRC Letter to YAEC, dated July 28, 1985 (NYR 86-162)
(h) YAEC Letter to USNRC, dated September 30, 1986 (FYR 86-091)
(i) USNRC Letter to YAEC, dated December 9, 1986 (NYR 86-273)
(j) YAEC Letter to USURC, dated February 13, 1987 (FYR 87-015)
Subject:
Regulatory Guide 1.97 - Probabilistic Risk Assessment Response to USNRC Safety Evaluation
Dear Mr. Fairtile:
The staff's safety evaluation for conformance of Yankee Nuclear Power Station with Regulatory Guide 1.97 was contained in Refetence (1). The evaluation concluded that Yankee either conformed to or had justified
)
deviations from the guidance of Regulatory Guide 1.97, except for the neutron flux variable when used for the long-term monitoring of positive reactivity addition events. Yankee had provided justification for this deviation in j
Reference (h) in which it was stated that there are two types of accidents that result in a harsh environment inside containment that could require long-term monitoring or reactivity, a primary system pipe break (LOCA) or a main steam or feedwater line break. However, for Yankee, the shutdown margin is maintained and a return to criticality is not a concern for either accident.
Yankee, in Reference (j), committed to provide further justification for its neutron flux variable position.
Attached is a risk-based analysis of the I
need for neutron flux indication for long-term monitoring of positive
[
reactivity addition events.
The analysis concluded that the potential for a 1
4 8710070208 871001 PDR ADDCK 05000029 1
P PDR y
{
t
s United States Nuclear Regulatory Commission October 1, 1987 Attention:
Mr. Morton B. Fairtile Page 2 core damage event was assessed to be extremely low, less than 10-7/ year and that no plant modifications are justified.
We trust that this submittal is satisfactory, however, if you have any questions, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY
)
a y
G. Papa c, Jr.
Senior Project Engineer Licensing i
l GP/15.194 l
cc:
USNRC Region i USNRC Resident Inspector - YNPS l
l l
l l
I
._ _._ _J