ML19256F667

Summarizes NRC Lessons Learned Implementation Team 791018 Telcon W/Util Re Response to NRC .Forwards List of Items Not Meeting Schedule & List of Items Needing Clarification

ML19256F667
Person / Time
Site:	Yankee Rowe
Issue date:	12/03/1979
From:	Burger A Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 7912190783
Download: ML19256F667 (5)

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December 3,1979 Docket No. 50-29 LICENSEE: Yankee Atomic Electric Company FACILITY: Yankee-Rowe

SUMMARY

OF NOVEMBER 14, 1979 PHONE CONVERSATION REGARDING LESSONS LEARNED IMPLEMENTATION During a phone conversation on November 14, 1979 the NRC Lessons Learned Implementation Team discussed with the licensee, its October 18, 1979 response to our September 13, 1979 letter.

The team informed the licensee of those lessons learned items for which the licensee's proposed schedule for implementation is unacceptable. These items, along with the proposed and required completion dates, are listed in Enclosure 1.

The team also informed the licensee of those items for which further clarifi-cation of the licensee's commitment is necessary to demonstrate compliance with the lessons learned requirements. These items and the associated team questions are listed in Enclosure 2.

Items 2.1.3.b (Instrumentation for Detection of Inadequate Core Cooling)

(Procedures Only), 2.1.7.a ( AFW Initiation), 2.1.7.b (AFW Flow), and 2.1.9 (Accident and Transient Analysis) were not discussed since these items are being implemented by the Bulletins and Orders Task Force.

By letter dated October 30, 1979 we provided additional clarification of the lessons learned requirements to all licensees. We also requested that within 15 days licensee's justify proposed actions not in complete agreement with the staff's requirements and improve the implementation schedule wnere it differed from the staff's requirements. During this phone conversation we informed the licensee that those items listed in Enclosure 1 should be addressed in their response.

In addition, the licensee agreed to provide the information requested in Enclosure 2 in its response to our October 30, 1979 letter or as soon thereafter as possible.

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%L %,s' s 9t e < i -g m Alfred Burger, Project Manager Operating Reactors Branch d2 Division of Operating Reactors

Enclosures:

1.

Items That Do Not Meet Schedule 1627 327 2.

Clarification of Licensee's Position Is Needed To Verify Comoliance 7 912190 7f)

. cc w/ enclosures:

Mr. Lawrence E. Minnick, President Yankee Atomic Electric Campany 20 Turnpike Road Westboro, Massachusetts 01581 Greenfield Community College 1 College Drive Greenfield, Massachusetts 01301 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Energy Facilities Siting Council 14th Floor One Ashburton Place Boston, Massacnusetts 02108 Director, Technical Assessment Division Of fice of Radiation Programs (AW-459)

U. S. Environmental Protection Agency

. Crystal Mall #2 Arlington, Virginia 20460 U. S. Environnental Protection Agency Region I Office ATIN:

EIS COORDINATOR JFK Federal Builaing Boston, Massachusetts 02203 Mr. Robert H. Grace Licensing Engineer Yankee Atomic Electric Company 20 Turnpike Rcad Westboro, Massachusetts 01581 1627 328

ENCLOSURE NO.1 YANKEE-ROWE ITEMS THAT 00 NOT MEET SCHEDULE 1.

Section 2.1.3.a - Direct Valve Position Indication The implementation of this item should be completed by January 1,1980 as discussed in the October 30, 1979 Harold R. Denton letter to all Operating Nuclear Power Plants.

2.

Section 2.1.3.b - Instrumentation for Detection of Inadeouate Core Cooling The installation of the subcooling meter should be completed by January 1, 1980 as discussed in the October 30, 1979 Harold R. Denton letter.

3.

Section 2.1.6.b - Shieldino Review Section 2.1.8.a - Post-Accident Samoling Our position is that the decision as to whether or not plant modifications are deferred in conjunction with the Systematic Evaluation Program (SEP) will be delayed until the design review information is available on January 1, 1980.

4 Section 2.l.4 - Containment Isolation Provisions Essential and Non-Essential systems should be identified and a basis should be given for the selection of each essential system. The extent of the modifications required will determine if this subject is appropriate for inclusion in the SEP.

5.

Section 2.1.8.b - Hiah Range Radiation Monitors By January 1,1980, you should provide an interim method for quantifying release rates for both noble gases and halogens if existing instruments are off-scale.

Implementation of necessary modifications should be achieved by January 1,1981 (Category B).

1627 329

ENCLOSURE NO. 2 YANKEE-ROWE CLARIFICATION OF LICENSEE'S POSITION IS NEEDED TO VERIFY COMPLIANCE 1.

Section 2.1.1 - Pressurizer Power Ooerated Relief Valves (PORV's) and Block Valves The intent of our position on energizing the PORV's and blocking valves from emergency power is to be assured by terminating pressurizer blowdown.

To this end the PORV and its blocking valve are to be energized from redundant trains. Your response did not address this issue. Please clarify this point.

Also, your response to our position did not address whether or not the devices that connect the pressurizer heaters, PORV's and block valves to the emergency buses are safety grade.

Please clarify this point.

2.

Section 2.1.3(a) - Direct Indication of Valve Position Your response to this Section did not address the guidelines in Harold R. Denton's October 30, 1979 letter.

Your clarification is required following the guidelines with particular attention to:

1)

Indication must be achieved in control room.

2) Equipment must be safety grade or have backup system.

3) Egipment must be seismic and environmentally cualified.

3.

Section 2.1.3(b) - Instrumentation for Detection of Inadeouate Core Coolina Your response indicates that major modifications to primary system are necessary. What are these modifications? You should also commit to a backup procedure to be implemented using steam tables and plant parameters.

4.

Section 2.1.6.a - Systems Integrity A program summary report should be submitted by January 1,1980 describing actions taken and planned. The report should include measured leak rates of existing systems and a description of the testing program.

1627 330

. 5.

Section 2.1.8.a - Post-Accident Samolino In addition to the design review, by January 1,1980 you should have both procedures and a description of the modifications needed to obtain and to analyze the necessary samples. Results should include H2 concentration in the containment atmosphere as well as dissolved gases (H2, 02) and B concentration in the primary coolant.

6.

2.1.8.c - Imoroved Radioiodine Instrumentation By January 1,1981 (Category B) you should have the added capability to purge the sampling cartridge and count it in a low-background area.

7.

2.2.2 B - Onsite Technical Succort Center Your response to this section did not address the specifics of the position as described in NUREG-0578. Your clarification is required.

8.

Section 2.2.2 C - Onsite Ocerational Sucoort Center Your response to this section did not address the specifics of the positions as described in NUREG-0578. Your clarification is required.

1627 331