View source for B11677, Advises of Current Plans to Address Requirements of 10CFR50.62,per Generic Ltr 85-06 Re QA Guidance for nonsafety-related ATWS Equipment

{{Adams
| number = ML20135E825
| issue date = 09/09/1985
| title = Advises of Current Plans to Address Requirements of 10CFR50.62,per Generic Ltr 85-06 Re QA Guidance for nonsafety-related ATWS Equipment
| author name = Opeka J
| author affiliation = CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = Thompson H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000000, 05000213, 05000245, 05000336, 05000423
| license number = 
| contact person = 
| document report number = B11677, GL-85-06, GL-85-6, TAC-59114, NUDOCS 8509170046
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
| project = TAC:59114
| stage = Other
}}

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HARTFORD. CONNECTICUT 0614bO270 L t   j ['j*['" "][fg",',                                            t203) 66s-5000 September 9,1985 Docket Nos. 50-213 50-245 50-336 50-423 Bil677 Director of Nuclear Reactor Regulation Attn: Mr. Hugh L. Thompson, Jr., Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Haddam Neck Plant Millstone Nuclear Pcwer Station, Unit Nos.1,2, and 3 ATWS Rule Schedule required by 10CFR50.62(d)
Generic Letter 85-06(l) provided quality assurance guidance for ATWS equipment that is not safety related and initiated the schedule detailed in 10CFR 50.62(d).         Specifically, 10CFR50.62(d) requires all light-water-cooled nuclear power plants to develop and submit a proposed schedule for meeting the requirements of 10CFR50.62 paragraphs (c)(1) through (c)(5). This letter is intended to advise you of Connecticut Yankee Atomic Power Company's (CYAPCO's) and Northeast Nuclear Energy Company's (NNECO's) current plans to address the requirements of 10CFR50.62.
Haddam Neck Plant Pursuant to H.L. Thompson's {{letter dated|date=July 31, 1985|text=July 31, 1985 letter}} (3), compliance with 10CFR50.62 for the Haddam Neck Plant will be evaluated as Topic 1.16 in the Integrated Safety Assessment Program (ISAP) review being performed for the Haddam Neck Plant. Among the inputs to this topic evaluation is a plant specific analysis provided to the NRC on February 28, 1975.(2) This analysis demonstrated that Haddam Neck would have a mild plant response to ATWS transients. In addition, plant modifications since 1975 (e.g. installing larger pressurizer PORVs) have further reduced the calculated consequences of an ATWS event. Our final plans and associated technical justifications will be submitted during the course of review of ISAP Topic 1.16 for the Haddam Neck Plant.
9509170046 850909 PDR       ADOCK 05000213 P                       PDR t
(1)      Generic Letter 85-06, H. L. Thompson to all applicants and licensees for                          g power reactor licenses, dated April 16,1985.
(2)
(3)
D. C. Switzer letter to A. Giambusso, dated February 28,1975.
H. L'. Thompson !ctter to J. F. Opeka, dated July 31, 1985.
[7   )   D
: s. m Millstone Unit No. I 10CFR50.62 specifies three separate requirements that are applicable to boiling
            . water reactors. These are:
(1)    Each boiling water reactor must have an alternate rod injection (ARI) system that is diverse from the reactor trip system from sensor output to the final actuation _ device. The ARI system must have redundant scram air header exhaust valves. The ARI'must be designed to perform its function in a reliable manner and be' independent from .the: existing reactor trip system from sensor output to the final actuation device.
            -(2)    Each boiling water reactor must have a standby liquid control system (SLCS) with a minimum flow capacity and boron content equivalent in control capacity to 86 gallons per minute of 13 weight percent sodium pentaborate solution. The SLCS and its injection location must be designed to perform its function in a reliable mancer. The SLCS Initiation must be automatic and must be designed to perform its function in a reliable manner for plants granted a construction permit af ter July 26,1984, and for plants granted a construction permit prior to July. 26,1984, that have already been designed and built to include this feature.
(3)    Each boiling water reactor must have equipment to trip the reactor coolant recirculation pumps automatically under conditions indicative of an ATWS.'
This equipment must be designed to perform its function in a reliable manner.
Millstone Unit No. I has an alternate rod insertion system that satisfies the requirements'of item (1), above. Millstone Unit No. I also has equipment to trip -
the recirculation pumps under conditions indicative of an ATWS that satisfies the .
requirements of item (3), above. Millstone Unit No.1 is equipped with a Standby
            - Liquid Control System (SLCS); however, the capacity of the SLCS does not meet the requirements of item (2) above. . The Millstone 1 SLCS has an equivalent control capacity of 43 gpm of 13 weight percent sodium pentaborate solution, which is half of the effective capacity required by 10CFR50.62.
Millstone Unit No. 1 is currently in compliance with the requirements of 10CFR50.62. concerning alternate rod Insertion. and recirculation pump - trip systems. Millstone Unit No. I does not meet the SLCS capacity requirement of 10CFR50.62. In accordance with Enclosure 2 to H.L. Thompson's {{letter dated|date=July 31, 1985|text=July 31,1985 letter}} (3) the~ significance of this difference and the need to increase.the SLCS capacity will be evaluated as Topic 1.18'in the Integrated Safety Assessment Program (ISAP) review being performed for Millstone Unit No.1.
Millstone Unit Nos. 2 and 3
                                      ~
NNECO, pursuant to the' paragraph (d) of 10CFR50.62, plans to request schedular
   .         relief from the completion date requirements'of 10CFR50.62 for Millstone Unit Nos. 2 and 3. Details of the extension requests, including proposed schedule for implementation and justification for delay, will be submitted by . October 14, 1985. it.is noted that the lengthy delay in the issuance of Generic Letter 85-06 is ' a key factor. regarding the need. for additional time to ' . complete implementation.
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                                                   -  3-We trust you will find this information satisfactory.                 Should you have any
 -        questions, my staff is available to assist you.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY
                                                                  /   *
: 3. F. Opdkal             U                                                           -
Senior Vice President l
cc:   Mr. John A. Zwolinski, Chief Operating Reactors Branch #5 Mr. Edward J. Butcher, Chief Operating Reactors Branch #3 l               Mr. B. 3. Youngblood, Chief
 !              Licensing Branch #1
!               Mr. C. I. Grimes, Chief Systematic Evaluation Programs Branch 4
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