ML19309E844
| ML19309E844 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Zion  |
| Issue date: | 02/20/1980 |
| From: | Telford J NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| Shared Package | |
| ML19309E842 | List: |
| References | |
| FOIA-80-186, RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8004240486 | |
| Download: ML19309E844 (5) | |
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O j(p" UNITED STATES 3x NUCLEAR REGULATORY COMMISSION j
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FIDRUARY 1 ' tEC DOCKET NO.! 50-247 LICENSEE:
Consolidated Edison Company FACILITY:
INDIAN POINT 2 STATUS REPORT ON SHORT TERM LESSONS LEARNED REQUIREMENTS On January 24 and 25, 1980, the Westinghouse TMI Lessons Learned implementa-tion team visited the Indian Point 2 Nuclear Power Station. The purpose of this visit was to determine the status of implementation of Category A (short tem) Lessons Learned requirements.
Indian Point 2 is currently shut down for inspection of turbine discs and plans to return to power in mid-February. Consolidated Edison Company, in a letter to the NRC on December 17, 1979, comitted to either completing all short term Lessons Learned items or alternately to remain shut down until they are complete. On the basis of this comitment, Consolidated Edison was issued confimatory letter by the NRC which specified that the NRC be notified in the event that any Lessons Learned item could not be fully implemented by the committed date.
The basis for judging acceptability of the implementation of each item is the requirements of NUREG-0578 and letter from Harold R. Denton to all operating nuclear power plants dated 10/30/79.
,s JNr. Telfofd Lessons Lear d Coordinator
Enclosures:
1.
Lessons Learned Status 2.
Attendance List
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LESSONS LEARNED STATUS Plant: Indian Point 2 Dates of Visit: January 24 and 25,1980 The following is the status of each Lessons Learned item based on the site visit t
by the Westinghouse implementation team. A list of attendees is attached.
i 2.1.1 Emergency Power Supoly IP-2 is in compliance with this item.
2.1. 2 Performance Testing of Relief and Safety Valves IP-2 participating in industry sponsored test programs which the NRC has agreed would satisfy this requirement.
2.1.3.a D1*ect Indication of Power-Ocerated Relief Valve and Safety Valve Polition i
IP-;'. does not fully meet the requirement in that the power-operated rel ef valve alarm is not actuated directly from the positive posi-tion indicating device but from a temperature indicating device in i
the discharge piping of the valve.
In addition, further clarification was requested from IP-2 to facili-tate NRC review of this item.
2.1.3.b Instrumentation for Detection of Inadeouate Core Cooling (Subcooling Meter)
IP-2 is in compliance with this requirement; however, additional clarification of their design is needed to complete the review.
IP-2 was also asked to provide more documentation on this item.
2.1.4 Containment Isolation IP-2 does not meet this requirement in t,he following respects:
1.
All non-essential systems are not automatically isolated.
2.
More than one valve is opened by a single action when non-essential valves are reopened following reset of the containment isolation signal.
2.1.5.a Dedicated Hydrogen Control Penetrations This item applies only to those plants that have external hydrogen recombiners.
IP-2 uses internal recombiners.
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I 2.1.5.c Capability to Install Hydrogen Recombiners at Each Light Water Reactor Plant IP-2 did provide procedures for use of their recombiners. They are in compliance with this item.
2.1.6.a Integrity of Systems Outside Containment Likely to Contain Radioactive Materials Program definition and record keeping of leak rate data was not yet established. A procedure review by the NRC OIE representative revealed several areas where improvements were needed. Although some itens remain to be completed, IP-2 is in essential compliance with this iten.
2.1.6.b Design Review of plant Shielding and Environmental Qualification of Eouipment for Spaces / Systems Which May Be Used in Post-Accident Operations Although IP-2 is in essential compliance with this item, two areas l
remain to be completed.
1.
Consideration and documentation of noble gas releases in auxiliary building, and 2.
Documentation of vital areas with specific dose rate data.
2.1.7.b Auxiliary Feedwater Flow Indication to Steam Generators IP-2 is in compliance with this item.
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t 2.1.8.a Improved post-Accident Sampling Capability l
IP-2 is in compliance with this item.
2.1.8.b Increased Range of Radiation Monitors IP-2 wes not in complete compliance with this item in that a method I
had r.ot been developed or implemented for monitoring radiation releases from the atmotpheric steam dump valves. Also, more informa-i tion was requested on method of determining release from the condenser
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air ejector.
2.1.8.c Improved In-plant Iodine Instrumentation Under Accident Conditions IP-2 is in essential compliance with this item, however, they were requested to document methods for use of silver zeolite cartridges.
2.2.1.a Shif t Supervisor Responsibilities i
IP-2 is in compliance with staff position.
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. 2.2.1.b Shift Technical Advisor IP-2 instituted necessary changes to be in compliance with NRC require-ment during the site visit. OIE will follow up to confirm.
2.2.1.c Shift and Relief Turnover Procedures IP-2 is in compliance with this item.
2.2.2.a Control Room Access IP-2 is in compliance with this item.
2.2.2.b On-Site Technical Support Center IP-2 is in compliance with this item.
2.2.2.c On-Site Operational Supoort Center IP-2 is in compliance with this item.
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Reactor Coolant System Vent Conceptual design of the RCS Vent was essentially complete.
IP-2 was asked to specify that venting would be in a good area in the containment.
During the meeting conducted at the conclusion of the staff visit, Consolidated l
Edison stated they would comply with all Lessons Learned requirements to the extent possible prior to returning to power. The only items questioned are the containment isolation provisions. The licensee will attempt to comply or to show that their system is equivalent to the staff position or is otherwise acceptabl e.
IP-2 agreed to provide documentation on items not complete or where they do not fully meet staff position prior to returning to power.
Items when they are in compliance as detennined by on-site staff review, all additional i
documentation requesteo will be included in a supplement to their implementation i
package. They will commit to a date for subnitting the supplement to their implementation package prior to returning to power.
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TMI IMPLEMENTATION SITE INSPECTIO*.4 EXIT MEETLNG JANUARY 25, 1980 ATTENDEES Nama Company D. M. Rosh Conn. Ed M. F. Shackouski Conn. Ed J. Kerrigan NRC/Lassons Learned A. Stakler EG&G R. J. Paolino NRC/IE C. Willis NRC/Lassons Learned N. Anderson NRC/Lassons Learned M. Fields NRC/ Lessons Learned J. Surdoin NRC/Lassons Laarned F. Rapose Conn. Ed W. Saunack NRC/IE Region I J. Johnson NRC/IE Region I S. Wisla NRC C. Limoges Conn. Ed J. Curry Conn. Ed P. M. Duggan Conn. Ed J. M. Makepeace Conn. Ed K. T. Eccleston Conn. Ed l
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