View source for A06657, Forwards Addl Info Re 861222 Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of License,Per NRC 870630 Request

{{Adams
| number = ML20236M908
| issue date = 08/04/1987
| title = Forwards Addl Info Re 861222 Application for Amend to License DPR-65,extending Duration of License to 40 Yrs from Date of Issuance of License,Per NRC 870630 Request
| author name = Mroczka E
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000336
| license number = 
| contact person = 
| document report number = A06657, A6657, TAC-64245, TQC-64245, NUDOCS 8708110297
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 9
| project = TAC:64245
| stage = Request
}}

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I               ,                                                 HARTFORD. CONNECTICUT 06141-0270 k     '   J  or a.c 4aa s rmecow .                                                   (203) 665-5000 August 4,1987.
Docket No. 50-336 A06657 Re: 10CFR50.51 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Additional Information for Forty-Year License Extension By letter - dated December 22, 1986,(1) Northeast Nuclear Energy Company (NNECO) requested an amendment to the Millstone Unit No. 2 Facility Operating License in order to extend the duration of the license to forty years from the date of issuance of the operating license.
In response to the NRC Staff's request dated June 30, 1987,(2) NNECO hereby provides the following additional information regarding the forty-year license extension amendment request.
NNECO believes that the attached information fully addresses the additional information requested by the Staff in Reference ' ,
Please contact us if you have any questions.
Very truly yours, NDRTHEAST NUCLEAR ENERGY COMPANY hh%)
E. 3. Mrfcika     f Ser3orNice President (1)   E. 3. Mroczka letter to A. C. Thadani, dated December 22,1986, " Millstone Nuclear Power Station, Unit No. 2, Proposed Amendment to Facility Operating License, Extension of Facility Operating License."
(2)   D. H. Jaffe letter to E. 3. Mroczka, dated June 30,1987, " Expiration Date                                                                             D A
for the Millstone Unit 2 Operating License (TAC #64245).
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U.S. Nuclear Regulatory Commission A06657/Page 2 August 4,1987                               .
cc:      W. T. Russell, Region 1 Administrator L
D. H. Jaffe, NRC Project Manager, Millstone Unit No. 2
                                            ' T. Rebelowski, Resident inspector, Mllistone Unit Nos. I and 2
                                                                                                                                                                                )

4' Docket No. 50-336 A06657 s
Attachment Millstone Nuclear Power Station, Unit No. 2 Additional Information for Forty-Year License Extension l
l l                                                                                                                                                                            l August 1987 1
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                                ' Attachment A06657/Page !
Question: - Briefly describe plant activities performed which contributed to the I;                                             high annual doses for 1978,1980,1982,1983,1985, and 1986.
Response: Below are listed the Millstone Unit.No. 2 annual exposure and PWR average exposures.
1978 1980 1982 1983 1985 1986 PWR - Average (man-rem)            428   578    578. 392         422                                         397 Millstone Unit No. 2 (man-rem)1621       638  1413 1881      1581                                            894 In all the aforementioned years, except 1980, steam ' generator inspection . and ~ repair projects were the ~ primary contributor ' to exposure above PWR averages. In 1980, Millstone Unit No. 2 was 58 man-rem above the average. Some problems encountered were stuck- in-core instrumentation.. and reactor head o-ring problems.
Please note that the 378 man-rem PWR average includes plants that did not have;a refueling outage during 1980. The Millstone Unit No. 2 total of 638 was probably less than the average for PWRs which had a refueling outage.
:In .1978,1270 man-rem were used for manual plugging of 762 tubes, pulling 48 tubes, and cutting tube supports. . In 1982,1090. man-rem were used for manual plugging of 707 tubes, replugging 49 tubes, nozzle dam problems, ECT/ finger walker problems, and a tube sample.
In- 1983, . approximately 1200 man-rem were used for the steam generators. Problems' consisted of unsuccessful automatic plugging and sleeving requiring manual . plugging and sleeving and .other
                                             - equipment problems. One hundred thirty-r x man-rem were used for thermal shield removal and outage extension added to the total.
In    1985,   964 man-rem were expended to           robotically sleeve approximately 2200 tubes and manually sleeve 700 tubes. Equipment problems also existed.
In 1986, approximately 200 man-rem were lost due to equipment problems including nozzle dam ' fit-up, steam generator tube restrictions, or misalignment and channel head decontamination residue. The duration of the outage (approximately 13 weeks) also contributed to the man-rem total.
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Attachment A06657/Page 2
                . Question: Describe any future expected major maintenance work to be performed at Millstone Unit No. 2.
Response: At present, steam generator replacement is a possibility. Estimated man-rem is 900-1400 man-rem.
Also, steam generator inspections and any necessary repairs - will continue. Our exposure goal of less than 300 man-rem per year includes such steam generator work.

       ' Attachment A06657/Page 3 Question: How do you plan to lower your annual collective doses in upcoming years?
Response:' NNECO is taking an aggressive :tand for the ALARA philosophy. The Exposure Reduction Initiative Program is a major effort on the part of NNECO to implement a number of projects with the primary intent to reduce man-rem. The attachment (which reflects our plans for four (4) Northeast Utilities plants) provides a list of specific projects being considered in the short and long term to carry out these initiatives.
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Attachment A06657/Page 4 i
Exposure Reduction Initiatives Initiative Number                                                                            Initiative Title Short-Term Initiatives ST No.1                 Increase ALARA Awareness--All Units ST No. 2                Job Cancellation / Scope Reduction--All Units ST No. 3                Work Practice Review--All Units ST No. 4                Construction Work Efficiency--All Units ST No. 5                Decontamination--CY, MP1, MP2 ST No. 6                CET Grayloc Flanges and Reactor Head Stud Tensioners--CY ST No. 7                Permanent Neutron Shield--MP2                                                                                         ;
ST No. 8                GEZIP--MP1 ST No. 9                Snubber Reduction--MP2, MP3 ST No.10                ALARA Installation Reviews--Early Stage--All Units ST No.11                Cobalt Reduction--All Units ST No.12                MP3 Project List ST No.13                Hydrogen Water Chemistry- MP1 Long-Term Initiatives LT No.1                 Decontamination Improvements--All Units LT No. 2                Longer Fuel Cycles--MP2, MP3, CY LT No. 3                Steam Generator inspection / Plugging Criteria--CY, MP2, MP3 LT No. 4                Primary Chemistry Controls--CY, MP2, MP3 LT No. 5                Robotics--All Units LT No. 6                Stearn Generator Replacement--MP2 LT No. 7                Cobalt Material Alternatives--All Units

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                  ' Attachment A06657/Page 5 -
Question: . Describe any future planned expansion'of on-site spent fuel storage capacity.(such as rod consolidation or dry storage) at Millstone Unit.
No.2.
Response: In May, 1986, al license amendment-- was' submitted to the NRC requesting ' authorization to store consolidated spent fuel in the Millstone Unit No. 2 spent fuel pool. On June 2,1987, the NRC issued a partial' approval of this amendment request which would allow the -
: storage of (5) consolidated' storage . canisters to support the. fue!
                                                                                                         .j consolidation hot demonstration. The NRC'is continuing to review the issues associated with the full scale stWa of consolidated fuel.
When; full scale storage is approved 'it will' provide' the increased storage capacity required to " bridge the time" until the Department of -
: Energy begins to accept fuel under the Nuclear Waste Policy Act.
The implementation of fuel consolidation at Millstone Unit No. 2, total utilization. of the existing spent fuel . racks, together- with improvements.in fuel design for longer. cycle life, can provide for "in pool" storage of all refueling discharges and maintain full core reserve space to the year 2015.
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                . Attachment A06657/Page 6
                 , Question: Address occupational exposure for the additional years of reactor operation.
Response: A number of significant ALARA measures have been incorporated since the initiation of the Millstone Unit No. 2 ALARA program in 1978. These include system decontamination (e.g., steam generators),
mock-up training, remote tooling and inspection techniques, extensive use of shielding, and special tooling, such as multistud tensioners. All of these measures will continue to the end of plant life, including the license extension period. Improvernents are expected in many of these ALARA measures. For example, full system decontamination may be possible, advanced robotic techniques will be developed, and improved chemistry controls should both lower dose rates and minimize the need for repairs.
It is our expectation that the man-rem / year will decrease with time from present levels. Millstone Unit No. 2 is actively seeking methods to reduce total man-rem. The goal is to average 500 man-rem / year or less. With this goal in mind, the extension of the extra few years of operation beyond the existing license should result in less than 2000 man-rem of occupational exposure. It should be noted that if the cost / benefit analysis for steam generator replacement proves advantageous, higher dose rates may be incurred with this endeavor.
Decommissioning is a one-time commitment and will be incurred with or without the extended license. Any increase in corrosion product buildup will be compensated for by improved chemistry controls to actually lower primary-side dose rates with time. Therefore, the extended operating time will have no measurable effect on decommissioning dose expenditures.                                                                                               l One of the primary f t.ases of the Health Physics program is to ensure compliance with the guidelines of 10CFR20 and the Technical Specifications. Such focus will continue until the end of the license.
Since implementation of the ALARA program in 1978 and establishment of administrative limits more restrictive than 10CFR20, no individual has exceeded the administrative limit of 5 rem / year at                                                           i Millstone Unit No. 2. We do not expect any problem in continuing this record through the end of plant life.}}