ML19323H904
| ML19323H904 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/12/1980 |
| From: | Moody D YANKEE ATOMIC ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.09 WYR-80-66, NUDOCS 8006170236 | |
| Download: ML19323H904 (6) | |
Text
9 Telephone 617 366-90ll e
TW1 710 390 0739 YANKEE ATOMIC ELECTRIC COMPANY s.s.2.1 WYR 80-66 h_
20 Turnpoke Road Westborough, Massachusetts 01581 AN KEE
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-. F June 12,1980 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Office of Nuclear Reactor Regulation Division of Licensing Darrell G. Eisenhut, Director
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) USNRC Letter to All Operating Reactor Licensees, dated March 7, 1980
Dear Sir:
Subject:
Five Additional TMI-2 Related Requirements Your letter, Reference (b), transmitted five items from the NRC TMI Action Plan which, applicable to operating reactors, constitute a second set of requirements for operating reactors. Yankee was requested to reply within 30 days of stating our commitments to meet the additional requirements and associated schedules. The attachment to this letter provides a tabulation of the items from Enclosure 1 of Reference (b) which are applicable to the Yankee Rowe plant and our implementation commitment for each item.
Please note the following comments relative to specific items:
Item I.A.l.3 - Yankee will respond to this item, Shift Manning, within 30 days of receipt of the material to be provided by your staff through separate correspondence.
Item II.K.3.9 - This item is not applicable to Yankee Ron as the plant does not have a PID type of controller on the PORV.
Item II.K.3 25, II.K.3 29, and II.K.3 44 - In accordance with discussions with your staff, these items are applicable to BWR's and, therefore, are not J
applicable to Yankee Rowe.
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Item III.D.3 4 - It should be noted that this item is also under review at Yankee Rowe as SEP Topic VI-8 with a site visit scheduled for April, 1981, and the safety assessment scheduled for completion in August, 1981. Although we
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have committed to meet the accelerated review schedule required by' Enclosure 1 of Reference (b), we would prefer to keep this as an SEP topic on the SEP schedule as it would be more compatible with our manpower scheduling.
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l, U. S. Nuclear Regulatory Commission June 12, 1980 Atter. tion: Darrell G. Eisenhut, Director Page 2 We trust you will finda this information satisfactory. However, if you have any questions, please contact us.
t Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY 4
D. E. Moody Manager of Operations
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Irplementation Sch?dula and Summary Item No.
_ Title Requirement Inplementatic' I.A.l.3-Shift Manning Yankee will make its commitment as to the scope and schedule of this requirement within 30 days of receipt of the details of the requirement.
I.A.3 1 Revise Scope and Submit revised programs.
Yankee's training programs were modified in con-Criteria for Licensing formance to the revised criteria Dorwarded in the Examination USNRC Letter of March 28, 1980 and were implemented prior to May 1, 1980 as requested.
Revised programs will be submitted to OLB for review by August 1, 1980.
I.C.5 Licensee Dissemination Perform an operating Yankee will review and revise all applicable pro-of Operating Experience experience assessment to cedures as necessary to assure that operating to Plant Staff assure that important information pertinent to plant safety, information is continually originating both within and outside the organi-provided to operators, zation, is continually supplied to operator and other personnel and is incorporated into plant tra'ning and retraining programs in accordance with the guidance provided in Enclosure 2 of the USNRC Letter of May 7,1980.
Yankee will complete the review and revision of applicable procedures by January 1,1981.
II.K.3 1 Isolation and Testing of (1) Licensee to document pro-If the results of the PORV failure studies Automatic PORV Isolation posed changes for staff specified in Action Item II.K.3 2 indicate that System approval prior to implemen-it is necessary to install a system to automati-tation.
Documentation to be cally isolate the PORV, Yankee will design and submitted by scheduled date.
install such a system.
(2) Licensee to implement Yankee will submit a proposed design by July 1, modifications and perform 1981 and implement and test at the next refueling conformatory test at the next outage following staff approval of the design, refueling outage following provided Action Item II.K.3.2 is completed as staff approval of the design scheduled.
unless this outage is scheduled within six months of the ap-proval date.
In this event, modifications will be completed during the following refueling outage.
Implementation Schedule and Summary Item No.
Title Requirement Implementa tion II.K.3.2 Vendor Report on PORV I
Provide report to staff.
1 Failure Reduction Yankee intends to participate in the vendor review of PORV failure rates and will submit the report by January 1,1981 if the vendor provides the report to Yankee in that timeframe.
The results of this review will be used to determine the necessity for the action requested in Item II.K.3.1 above.
II.K.3 3 Report 3 ng Safety and Relief talve Failures Provide an annual report on SRV and RV failures and In the event of safety valve and relief valve challenges as of Jan.1,1981.
failures and challenges, Yankee will provide an and Challenges annual report as of January 1,1981.
II.K.3 5 Automatic Trip of RCP During a LOCA Provide the results of an evaluation of alternative The existing rationale for tripping reactor solutions to RCP trips.
coolant system pumps during a small LOCA is based solely upon the results of vendor sensitivity studies of pump operating phenomena during a LOCA.
Any conclusions derived from these results should carry with them the same uncertainty associated with the models and methods used to achieve the results.
Currently, NRC is requiring small break model verification against semiscale and LOFT experiments to prove the validity of vendor models.
Yankee intends to verity its small break LOCA models against experimental data and upgrade them as required. However, to date, no conclusive evidence has been gained in the semiscale program to support the automatic tripping of the reactor coolant pumps.
The earliest pump effects test data from LOFT will l
not be available until December 1980.
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Irplementation Schedule and Summary Item No.
Title Requirement Implementation II.K.3.5 Automatic Trip of RCP It is currently counterintuitive to (Cont'd)
During a LOCA automatically trip the RCP's based upon the results to date. Yankee-desires to pursue other alternatives to tripping the pumps -- improved ECCS, plant specific analysis to determine operability of our RCP's.
However, any serious plant modification such as the automatic tripping of reactor coolant pumps should be based on believable and approvable models.
Therefore, Yankee will at this time commit to study the RCP problem and institute any design changes deemed necessary only after the small break LOCA methodology has been proven and experimentally verified through our participation in the action plans specified in II.K.3 30 and 31.
In the interim, the manual reactor coolant pump trip procedure will remain in place. This is the most prudent, safety consciotis action at this time. It provides ample protection against detrimental RCP operation during a small break LOCA while at the same time maintaining the probability of a complete loss of flow accident at existing levels. This is a crucial item for Yankee Rowe since the RCP's have no fly wheels and very limited coastdown capability.
II.K.3.9 PID Controller Modification The item does not apply to Yankee as Yankee does not have a PID controller.
II.K.3.10 Anticipatory Trip Document proposed char.ge Yankee confirms that it has an anticipatory II.K.3 12 and implement modification.
reactor trip on turbine trip which is effective at power levels above 15 MWe.
Yankee has no plans to change this set point.
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17plementation Schedulo end Summary Item No.
Title Requirement Implementation II.K.3.17 Report on Outage of Provide a report detailing Yankee intends to submit a report on the outage ECCS During the Last outage dates, and lengths of ECC Systems by January 1,1981.
Five Years of outages for all ECCS for the last five years of.
operation.
s II.K.3 30 Revised SB-LOCA Methods Submit analysis model for Yankee intends to revise small break LOCA. methods to Show Compliance with staff approval.
to show compliance with 10 CFR 50, Appendix K by 10 CFR 50, Appendix K July 1,1983 II.K.3 31 Plant Specfic Calcula-Submit the results of an Yankee it.' ends to perform these plant specific tions to Show Compliance evaluation to the staff.
calculations one year after NRC approval of with 10 CFR 50.46 small break LOCA methods revised in accordance with Item II.K.3 30 above.
III.D.3.4 Control Room Assure that control room Yankee intends to perform a study of control room Habitability operators will be adequately habitability in conformance with the guidance protected against the provided in Enclosure 4 of the NRC Letter of effects of accidental May 7, 1980. The results of the study will be release of toxic and submitted by January 1,1981.
In order that the radioactive gases.
implementation of changes may be coordinated with the modifications resulting from other SEP Topic reviews, Yankee intends to implement any modifications on the SEP schedule.
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