ML19309E847
| ML19309E847 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Zion  |
| Issue date: | 02/15/1980 |
| From: | Telford J NRC - NRC THREE MILE ISLAND TASK FORCE, NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | NRC - NRC THREE MILE ISLAND TASK FORCE, NRC OFFICE OF STANDARDS DEVELOPMENT |
| Shared Package | |
| ML19309E842 | List: |
| References | |
| FOIA-80-186, RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8004240489 | |
| Download: ML19309E847 (8) | |
Text
{{#Wiki_filter:_ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _. O. j e a' soy fi k UNITED STATES e( g NUCLE /.R REGULATORY COMMISSION g' .-l wasmuorow. o. c. 2 ossa %v / February 15, 1980 DOCKET NO. 50-286 APPLICANT: POWER AUTHORITY OF THE STATE OF NEW 10Z FACILITY: INDIAN POINT 3
SUMMARY
OF MEETINGS ON JANUARY 23, 24 AND JANUARY 30, 1980 TO DISCUSS SFORT TERM LESSONS LEARNED REQUIEMENTS Enclosed are summaries of two site visits to Indian Point 3. The purpose of the first site visit by the Westinghouse implementation team to Indian Point 3 on January 23, 24, 1980 was to identify the problem areas, if any, in the implementation of the short-term Lessons Learned. During our re-view, it was discovered that some items were not in full compliance with NRC requirements; some were not complete and additionaJ information_ was required on others to determine the extent of compliance. Enclosure 1 is a brief status of these items. At the exit interview, Indian Point 3 plant management was informed of our findings. They agreed to make modifi-cations as necessary to meet all short term requirements. They also agreed to provide the requested information prior to returning to power. On Januar r 30, 1980, the Lessons Learned Coordinator, J. Telford, and the Westinghcase Lessons Learned team leader again visited the IP-3 site to determine the extent of compliance of all outstanding items. Enclosure 2 is a brie ' summary of each item. During this visit, it was determined that IP-3 had a mpleted all items except 2.1.6.b and 2.1.4. On 2.1.6.b, shieldir.g t wiew, IP-3 expected to complete the one remaining item the afcernoon or evening of January 30, 1980. The licensee was told that their containm at isolation system would be acceptable on an interim basis provided that addnistrative controls be implemented for the re-opening of certain non-essential systems following a containment isolation signal. Subsequent conversations with the licensee and the I&E resident inspector have confirmed that 2.1.6.b has been completed and that procedures are in place for 2.1.4. Based on these site visits and the documentation received from the licen-see, we conclude that IP-3 seats all short term Lessons Learned requirements. % T. Telfsd Lessons Learned Coordinator Eaclosures: See Page 2 800 4240 5-{ p
Meeting Summary for February 15, 1980 Indika Point 3
Enclosures:
1. 1-23, 24-90 site visit 2, 1-30-80 site visit ~ cc: White Plains Public Library Mr. J. P. Bayne, Resident Manager 100 Martine Avenue Indian Point 3 Nuclear Power Plant White Plains, New York 10601 P. O. Box 215 Buchanan, New York 10511 Mr. Vito J. Cassan Assistant General Counsel Mr. J. W. Blake, Ph.D., Director Pover Authority of the Environmental Programs S: ate of New York Power Authority of the 10 Columbus Circle State of New York New York, New York 10019 10 Columbus Circle New York, New York 13019 Anthony Z. Roisman Natural Resources Defense Council Theodore A. Rebelowski 917 15th Street, N.W. U.S. Nuclear Regulatory Commission Washington, D.C. 20005 P.O. Box 38 Buchanan, New York 10511 Dr. Lawrence D. Quarles Apartment 51 Ms. Ellyn Weiss Kendal at Longwood Sheldon, Harmon and Weiss Kennett Square, Penn. 19348 1725 I. Street, N.W. Suite 506 Mr. George M. Wilverding Washington, D.C. 20006 Licensing Supervisor Power Authority of the State of New York 10 Columbus circle New York, New York 10019 Mr. P. W. Lyon Manager - Nuclear Operations Power Authority of the State of New York 10 Columbus Circle New York, New York 10019 l
Meeting Sumary for Indian Point 3 February 15, 1980 c Docket Files NRC POR Local PDR } ORB 1 Reading NRR Reading H. Denton E. Case D. Eisenhut R. Tedesco G. Zecn B. Grimes W. Gamill L. Shao J. Miller R. Vollmer T. J. Carter A. Schwencer D. Ziemann P. Cneck, G. Lainas D. Crutchfield
- d. Grimes i
T. Ippolito R. Reic V. Noonan G. Knighton D. Brinkman Project Manager OELO OI&E (3) C. Parrish/P. Kreutzer ACRS (16) I IsC Participants teilC TERA Licensea Short Service List I i l l 1
LESSONS LEARNED STATUS Plant: Indian Point 3 Dates of Visit - January 23, 24, 1980 Implementation Category: Confirmatorv Letter The following is the status of each Lessons Learned item based on the site visit by the Westinghouse implementation team. A list of attendees is attached. 2.1.3.a Direct Indication of PORV and SV Valve Positions Additional information is required on the manufacturer's specifications for the acoustical monitoring system. Verification that emergency pro-i cedures are available to the operator for use as a backup indication of valve opening is required. 2.1.3.b Subcooling Meter j Licensee's method for determining subc,oling is not in compliance f with all L2 requirements. Licensee agreed to use their backup method which involves using the plant computer as the primary indication of i subcooling. This second system uses incore thermocouple temperatures as input. While this system meets our requirements, additional docu-mentation and backup procedures for calculating subcooling using the steam tables is required. 2.1.4 Containment Isolation [ IP-3 does not meet the staff position with regard to containment isola-l tion reset. IP-3 must provide additional justification prior to restart. 2.1.6.a Systems Integrity Documentation on this item was not complete. Additional justification for systems excluded from the program and documentation of leak rate data must'be provided. 2.1.6.b Shielding Review The licensee has not completed the assessment of safety equipment that must function in the radiation fields during an accident. This analysis must be completed and documented. 2.1.8.a Post Accident Samoling Training was not com,plete and some of the equipment was not yet installed at the time of the site visit. Work was in progress on this item. l
. 2.1.8.b High Range Radiation Monitors I The licensee did not have a meched for measuring accidental releases via steam dump / safeties; this must be developed and documented prior to plant restart. 2.2.1.a Shift Turnover Procedure The licensee must Laplement formal shif t turnover procedures for shif t supervisor during an accident. The licensee has agreed to modify this procedure. OIE will follow up. 2.2.1.b Shift Technical Advisor The licensee must relieve STA from the responsibility of initiating [ manning of the onsite Tech Support Center. They agreed to modify their procedures in this regard. OIE will follow up. 2.2.2.c Onsite Operational Support Center Onsite operational supp. ort center communication link was not installed. Licensee agreed to install before returning to power. OIE will confirm. IP-3 agreed to provide certification that all items are complete and t'o make modifications required by the staff and to document changes and provide clarifica-tion prior to restart. OIE will follow up as indicated. z f ] i i \\ 1
t Accachment 1 LIST OF ATTENDEES Power Authority of the State of New York i S. Zulla E. Tagliamente M. Albright W. Jossiger J. Kelly P. Bayce W. Hamlin S. Munoz C. Caputo J. Vigard. B. Brocxcank NRC N. Anderson M. Fields C. Willis J. Burdoin J. Kerrigan J. Johnson, OIE W. Baunack, OIE A. Stalker (consultant, EG&G) e
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4 LESSONS LEARNED STATUS REPORT Plant: Indian Point 3 Date of Visit: Januarv 30, 1980 The following is the status of Lessons Learned items following plant visit on 1/30/80 by J. T. Te'1 ford and N. Anderson and preliminary review of the licensee's 2/3/80 submiccal. Only those items which were not in full compliance or incom-plete when the plant was visited on 1/23, 24/80 are addressed. 2.1.3.a Dirmet Indication of PORV and SV Valve Positions IP-3 had addressed all staff concerns. They are using manufacturer's specifications for the acoustical system and documented that the PORV's are using the acoustical system. All required procedures are written and in force but need to be formally documented. Also needed is the schedule for completion of the qualification program and a confirmation that the power supply for this system comes from a vital l instrument bus. 2.1.3.b Subcooling Meter The system that uses the plant computer to calculate subcooling condi-tiens meets the staff's requirements. The following additional informa-tion must be provided: (1) the schedule for upgrading pressure sensors to same quality as other ESF equipment, (2) a reliability assessment for the plant computer; and (3) che table for this system required by the October 30 letter. 2.1.4 Containment Isolation IP-3 agreed to Laplement administrative controls for the control of isolation valves not on automatic isolation (normally locked out) and for the reopening of non-essential isolation valves that can be opened more than one at a time by a single action (i.e., a single acticn opens more than one valve). The staff agreed to accept the containment isolation system on an interim basis with the procedural controls in effect. 2.1.6.a Systems Integrity The licensee's 2/3/80 subaittal: (1) lists and justifies excluded systems, (2) includes the volume control tank and (3) provides leak race data. The licensee agreed to provide a more complete program description. l t l t
a - 2.1.6.b Shieldina Review The new submittal reports the preliminary review of equipment environ-mental qualification as required by short term Lessons Learned. The more complace study is sheeduled for April 30, 1980. 2.1.8.a Post Accident Sampling The licensee's 2/3/80 submittal confirms that installation of equip-ment is now complete. The adequacy of training in new sampling procedures will be verified by OIE. 2.1.8.b High Range Radiation Monitors Provisions have now been made for monitoring the steam dump / safeties release path. 2.2.1.a Shift Turnover Procedures Required changes had been made to procedures to ecmplete this item. 2.2.1.b Shift Technical Advisor ' ~ ' Required changes had been made to bring this item into compliance with staff position. 2.2.2.c Onsite Operational Support Center The communication link between the onsite operational support center and the control room had been installed and is functional. <}}