ML20235U217
| ML20235U217 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/16/1987 |
| From: | Papanic G YANKEE ATOMIC ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| FYR-87-75, NUDOCS 8707220397 | |
| Download: ML20235U217 (3) | |
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l' Telephone (617) 872 8100 ll TWX 710 380 7619 YANKEE ATOMIC ELECTRIC COMPANY j e-AE*N 1671 Worcester Road. Framingham, Massachusetts 01701
,Y'AN K EE
- * 'j July 16, 1987 FYR 87-75 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) Letter, USNRC Region 1 to YAEC, Inspection No. 50-29/87-05, dated ~ June 2, 1987
Subject:
Emergency Response Facilities Audit, Open Items
Dear Sir:
Reference (b) is the Region 1 inspection report of the Emergency Response l
-Facilities.(ERFs) appraisal conducted at the Yankee Nuclear Power Station during the period of March 30, 1987 through April 3, 1987. The purpose of this letter is to respond to the open items identified in Reference (b) as Appendix B.
1.
.Open Item No. 2 (50-29/87-05-03) states, " Perform a review and analysis of the Telecommunications System linking the plant SPDS with the EOF."
YAEC Response The Telecommunications System failures, which occurred during the audit have been reviewed and analyzed, after discussions with New England Telephone (NET) and American Telephone and Telegraph (AT&T)
Communications.
The failures witnessed during the audit were of one-minute and three-minute duration.
Since the line outage time was too short to trace the fault, the severe weather conditions at the time are suspected.
The statistics were reviewed to determine the availability of the SPDS to EOF data flow. Based on data between March 11, 1986 through April 2, 1987, the availability was 99.37%. Had an actual unusual event taken place during the communications system downtime, the dial backup system could have been initiated within 30 minutes.
HEE 0397870716 o
ADOCK 05000029 PDR y
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. sh United States Nuclear Regulatory Commission
' July 16 1987 Attention: Document Control Desk Page 2 FYR 87-75 2..
Open~ Item No. 5 (50-29/87-05-04)~ states, "The, license'e does not have i
l the. capability to calculate'a' site boundary. thyroid dose from.tne
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Control Room'and TSC."
e
'YAEC Response i
Three new nomograms for calculating site boundary thyroid dose rates for the vapor container leakage, primary vent stack, and main steam line release pathways will be generated..In addition, the hand-held-programmable HP41-C calculation methodology currently used by.the Cantrol j
Room and TSC personnel to project whole body dose rates at site boundary, will be upgraded to also project site boundary thyroid' dose rates. These I
methodologies will produce thyroid dose rate projections based on i
existing radiation monitor readings (high range l noble gas stack monitor, high range. containment monitor..and main steam line radiation monitor) using a pre-determined, pathway-specific ratio of curies of iodine released to curies of total noble' ras released. 'The. nomogram methodology, including training,'ill-be completed by the end of February.1988..
.{
The HP-41C methodology, including training, will be' completed by the end
'of June 1988.
3.
Open' Item No. 4'(50-29/87-05-05) states, "The licensee does not have' the' capability to calculate release. rates.from the Safety Injection (SI) Building, or the subsequent whole body and thyroid dose from an SI Building release."
YAEC Response A procedure will be developed and implemented for estimating release rates (e.g.. building atmospheric concentrations and exit flow rates) from the SI Building. These release rates will then be available for input into a planned modification of the METPAC dose assessment model which will be used to calculate. thyroid dose rates (whole body dose rates from an SI Building release would be negligible).
The activities described above, including training, are expected to be completed by the end of March 1988..
4.
Open Item No. 5 (50-29/87-05a06) states, "The licensee does not have the capability to utilize post-accident Reactor Coolant Sample results for performing dose calculations."
.YAEC Response l
Reactor coolant sample results are an input into the evaluation of core condition following a severe accident. 1here is, however, no direct correlation between reactor coolant concentrations and off-site doses.
1 1
United States Nuclear Regulatory Commission July 16, 1987 Attention: Document Control Desk Page 3 FYR 87-75 Yankee believes that off-site doses are best projected based on containment air concentrations and on release point radiation monitor readings since these can be correlated to off-site concentrations.
l Through the use of the primary or a!.cernate containment atmosphere l
sampling locations, we are capable of obtaining the needed samples. No l
further action is planned for this item since Yankee evaluates this l
method to be timely and reliable.
i If you have any questions concerning the above, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY L
Aso!
George ic, Jr Senior Project Engineer, Licensing G?/25.41
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