ML20246L327
| ML20246L327 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/04/1989 |
| From: | Zech L NRC COMMISSION (OCM) |
| To: | Markey E HOUSE OF REP. |
| Shared Package | |
| ML20246L331 | List: |
| References | |
| TASK-1.D.1, TASK-2.B.3, TASK-2.F.1, TASK-3.A.1.2, TASK-TM NUDOCS 8905180296 | |
| Download: ML20246L327 (4) | |
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UNITED STATES -
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g NUCLEAR REGULATORY COMMISSION g
a-p WASHINGTON, D. C. 20556
%,,,,,y May.4, 1989 CHAICMAN :
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The Honorable Edward J. Markey
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' United States House of Representatives
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Washington, D.C.
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Dear Congressman Markey:
1 At your request, I am enclosing the NRC staff's respense to the sixth question contained in your letter of March 23,1989, concerning the status of Three Mi.le Island action items.
As I explained'previously,.the Commission wishes to ensure that its responses to your questions are as thorough,' complete, and accurate as possible. The_ staff is currentlyJin the process of providing us such assurance. When that effort is complete, the-Commission will respond to all the questions in your letter.
j Should you have any questions concerning this matter, please call me.
Sincerely,.
'l Lando W. Zech r.
Enclosure:
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8905180296 890504 8-g PDR. COMMS NRCC CORRESPONDENCE PDR
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ENCLOSURE l
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Question and Answer Concerning the Status of TMI Action Plan Requirements at Seabrook QUESTION 6 What is the status of TMI Action Plan requirements at the Seabrook nuclear power plant?
ANSWER i
l The NRC staff has recently completed a review of the status of all TMI Action Plan items at Seabrook. As described below, three TMI Action Plan items remain to be completed and three others that have been implemented require confirmatory actions by the licensee.
Before these confirmatory actions can be completed, however, specific plant conditions, including operation at power, must be 1
achieved. These conditions cannot be met at the current tage of facility licensing. All other applicaule TMI Action Plan items at Seabrook have been completed.
A.
TMI Action Plan Items To Be Completed 1.
III.A.2.1 - Upgrade Preparedness - Upgrace Emergency Plans to Appendix E 10CFR 50 Two actions remain to complete this iten:
Implementation of the Public Alert and Notification System in F lsachusetts and final distribution of public
. information brochures. These are awaiting completion of ASLB Emergency Prepared-ness Hearings on the Massachusetts portion of the Seabrook Emergency Planning Zone. The licensee will complete these actions after the hearings and prior to i
1 issuance of a full power license.
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III.D.3.4.3. - Control Room Habitability - Implement Modifications Actions required to complete this item for power levels up to 5% have been completed and approved by the staff.
Before exceeding 5% power, the licensee will implement a design change to bring the control building air system into i
conformance with the Standard Review Plan and General Design Criterion (GDC)
- 19. As presently constructed, control room pressurization could be compromised 1
under certain conditions of a vital bus failure coupled with a design basis
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accident. Although acequate for operation at less than 5% power, this potential failure mode must be corrected before power operation. The NRC staff approved the licensee's design change on August 24, 1988.
Implementation of I
this design change will close this item.
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I.D.2.3 - Plant Safety Parameter Dieglay System (SPDS) Fully Implerynted I
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The SPDS has been installed. Several system software changes are being imple-l mented and will be completed by May 31, 1989.
In accordance with an ASLB March 25, 1987 Partial Initial Decision, as it relates to the SPDS, system availability calculations and a load test must be conducted and reported to NRC staff. This cannot be completed until power operation.
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TMI Action Plan-Items Requiring Confirmatory Action 1.
I.D.1 - Control Room Design Reviews The licensee has committed to provide an evaluation of the control room environ-ment confirming the acceptability of parameters that will not be available until power operation (e.g., temperature, noise, humidity). All other aspects of this item are complete.
2.
11.B.3.4 - Post-Accident 5arupling - Plant Modifications The Post-Accident Sampling System is complete but must be tested to show it will perform its intended function.
Reactor coolant system activity is requireo to verify operability.
Subsequent to low power testing, and prior to issuance c+ a full power license, confirmatory testing will be corrpleted.
3.
II.F.1.2.8 - Accident Monitoring - Iodine / Particulate Sample I
All needed instrumentation has been installed.
Operability of the system has been recently demonstrated by using modeling and analysis by the licensee.
The results of the modeling, which indicate acceptable transmission factors for gaseous effluent sample lines, are to be documented in a report to be submitted to NRC by May 30, 1989. Confirmatory testing of the system under actual plant conditions cannot be accomplished without the presence of recctor coolant activity; however, the modelino and ar.alysis approach has been accepted by the NRC staff.
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