ML20137C834

Forwards Changes to Final Draft Tech Specs.Reaffirmation of Certification That Tech Specs Reflect,In All Matl Aspects, as-built Plant Configurations,Fsar Through Amend 16 & SER Through Amend 3 Requested

ML20137C834
Person / Time
Site:	Millstone
Issue date:	11/20/1985
From:	Youngblood B Office of Nuclear Reactor Regulation
To:	Opeka J NORTHEAST NUCLEAR ENERGY CO.
References
NUDOCS 8511260621
Download: ML20137C834 (8)

Text

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NOV 2 01985 Docket No.: 50-423 Mr. J. F. Opeka Senior Vice President Nuclear Engineering and Operations Northeast Nuclear Energy Company P. O. Box 270

Subject:

Final Technical Specifications for Millstone Nuclear Power Station, Unit 3 In a letter from you to Mr. Hugh L. Thompson, Jr. dated November 15, 1985, you certified that, to the best of your knowledge, the final draft Technical Specifications transmitted to you on November 8,1985, with the inclusion of changes identified in your letter reflect in all material aspects the as-built plant configuration, the Final Safety Analysis Report through Amendment 16, and the NRC Staff's Safety Evaluation Report, through Amendment 3, and other docketed correspondence with the NRC staff.

The staff has since identified several necessary changes to the final draft Technical Specifications which are included as Enclosure 1. Please review these changes and, if appropriate, reaffirm your certification.

Sincerely M 1 B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing

Enclosure:

As stated cc: See next page Distr'bution: ~

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s. Mr. J. F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 3 cc:

Gerald Garfield, Esq. Ms. Jane Spector Day, Berry & Howard Federal Energy Regulatory Commission City Place 825 N. Capitol Street, NE Hartford, Connecticut 06103-3499 Room 8608C Washington, D.C. 20426 Mr. Maurice R. Scully, Executive Director Connecticut Municipal Electric Energy Cooperative 268 Thomas Road Groton, Connecticut 06340 Robert W. Bishop, Esq.

, Corporate Secretary Northeast Utilities Post Office Box 270 Hartford, Connecticut 06141 Mr. T. Rebelowski Senior Resident Inspector Office t U. S. Nuclear Regulatory Commission Millstone III P. O. Box 615 Waterford, Connecticut 06385 Mr. Michael L. Jones, Manager Project Management Department Massachusetts Municipal Wholesale

. Electric Company l Post Office Box 426 Ludlow, Massachusetts 01056 l

i Regional Administrator U. S. NRC, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406

_ .s Mr. Karl Abraham Public Affairs Office, Region I U. S. Nuclear Regulatory Commission, King of Prussia, Pennsylvania 19406 l

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS .

SECTION -

PAGE l

3/4.8 ELECTRICAL POWER SYSTEMS _

3/4.8.1 A.C. SOURCES 0perating................................................ 3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................ 3/4 8-8 )

i Shutdown................................................. -

3/4 8-9 3/4.8.2 D.C. SOURCES l 0perating................................................ 3/4 8-10 TABLE 4.8-2a BATTERY SURVEILLANCE REQUIREMENTS.................... 3/4 8-12  ;

TABLE 4.8-2b BATTERY CHARGER CAPACITY............................. 3/4 8-13

[r Shutdown................................................. 3/4 8-14 i 3/4.8.3 ONSITE POWER DISTRIBUTION .

Operating................................................ 3/4 8-15 t

Shutdown................................................. 3/4 8-17

, 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcerrent Protective Devices.......................................t 3/4 8-18

, TABLE 3.8-1 CONTAINMENT. PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES....................................... 3/4 8-20 Motor-Operated Valves Thermal Overload Protection........ ' 3/4 8,#1'2e

! TABLE 3.8-2a MOTOR-0PERATED VALVES THERMAL OVERLOAU PROTECTION BYPASSED ONLY UNDER ACCIDENT CONDITIONS.................. 3/4 8.Af"29 f ~

Motor-Operated Valves Thermal Overload Protection ,

'l Not Bypassed............................................. 3/4 8-f5' 32.

TABLE ~3.8-2b MOTOR-0PERATED VALVES THERMAL OVERLOAD PROTECTION i NOT BYPASSED............................................. 3/4 8-A8 33 A.C. Circuits Inside Containment......................... 3/4 8-5dF1F7 3/4.9 REFUELING OPERATIONS -

3/4.9.1 BORON CONCENTRATION...................................... 3/4 9-1 3/4.9.2 INSTRUMENTATION.......................................... 3/4 9-2 3/4.9.3 DECAY TIME.............................................?w. 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS. . . . . . . . . . . . . . . . . . . . . . . . 3/4 9-4

) 3/4.9.5 COMMUNICATIONS........................................... 3/4 9-5 MILLSTONE - UNIT 3 xi t

, . , . , - - - - - - -,, ,-,_..,n.- ,--,,,,---,,,.,,---,y -

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D TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION p' .

MINIMUM INSTRUMENT LOCATION -

OPERABLE

1. Wind Speed

. ws-13 E'3 b. --

SS, I

.h g. WS-142 Nominal Elev. 142' I c ). WS-374 Nominal Elev. 374' 1

2. Wind Direction

. wb-33 W N. 33, I

.b g. WD-142 Nominal Elev. 142' I

c. g. WD-374 Nominal Elev. 374' 1

! 3. Air Temperature - AT* *

a. DT-142 Nominal Elev. 142' I i b. DT-374 Nominal Elev. 374' 1 i .

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• Group reference is 33'. AT is the bdifference  ::!:eltt:d between the

• n temperature at 33' and the temperature at elevations 142' and 374} 3-sp

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MILLSTONE - UNIT 3 3/4 3-51 _

p. . , p -, , , - - - - - - - , - - , , - - - - - , , ,

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'n TABLE 4.3-5 METEOR 0 LOGIC L MONITORING INSTRUMENTATION g'.

' SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL -

INSTRUMENT CHECK CALIBRATION

1. Wind Speed

a. T_ .

• 3 N . 33' D SA L p. Nominal Elev. 142' D SA c )(. Nominal Elev. 374' D SA

2. Wind Direction

.. %4 E1 ,. 39 D SA b g. Nominal Elev. 142' D SA c jf. Nominal Elev. 374' D SA r

3. Air Temperature - AT o-- o

a. Nominal Elev. M 11 - 142 D SA bl Nominal Elev. F SS b74.# . D SA

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,_ , - _ - - . - _ , _ , - - - . - _ - - - , - - - . - - - - . _ - - _ _..-s _ , . - - - -

'l f

PLANT SYSTEMS SURVEILLANCE

• REQUIREMENTS (Continued) r' .

c. VisualinspectionAcceptanceCriteria Visual inspections shall verify that: (1) there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the . foundation or supporting structure are functional, and (3) fasten-ers for attachment of the snubber to the component and to the snubber l anchorage are functional. Snubbers which appear inoperable as a l

result of visual inspections may be determined OPERABLE for the l purpose of establishing the next visual inspection interval, provided that: (1) the cause of the rejection is clearly established end ,

remedied for that particular snubber and for other snubbers irrespec- l tive of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and deter-mined OPERABLE per Specification 4.7.10f. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

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d. Transient Event Inspection e

An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 6 months following such an event. In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least.one of the following: (1) manually induced snubber movement; or-(2) evaluation of in place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.

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( e. Functional Tests

-l During the first refueling shutdown and at.least once per 18 months thereafter during shutdown, a representative sample of snubbers of

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each type shall be tested using one of the following sample plans.

The sample plan for each type shall be selected prior to the test period and cannot be ' changed during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan selected for each snubber type prior to the test period or the sample plan used in the prior test period shall be implemented:

1) At least 10% of the total of each type of snubber shall be -

functionally tested either in place or in a bench test. For g each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.10f.,'an additional JE ,

of that type of snubber shall be functionally teste.d until no more failures are found or until all snubbers of that type have been functionally tested; or s .

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e PLANT SYSTEMS -

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V,\

BASES -

1 SNUBBERS (Continued) has elapsed may be used as a new reference point to determine the next. inspection. .

However, the results of such early inspections performed before-the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

The acceptance criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers. For example, if a fluid port of a hydraulic

~

• snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.

To provide assurance of snubber functional reliability,.one of three

! functional testing methods is used with the stated acceptance criteria:

1. Functionally test 10% of a type of snubber with an additional '

Jef tested for each functional testing failure, or

! 2. Functionally test a sample size and determine sample acceptance or rejection using Figure 4.7-1, or

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3. Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.

Figure 4.7-1 wa~s developed using "Wald's Sequential Probability Ratio i ~ , Plan" as described in " Quality Control and Industrial Statistics" by

'Acheson J. Duncan.

3

~ Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the com-4

• pletion of their fabrication or at a subsequent date. Snubbers so exempted l

shall be listed in the list of individual snubbers indicating the extent

_ .,of the exemptions.

The service life of a snubber is established via manufacturer input and '

information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance ~ evaluation in view of their age and operating conditions. These records will provide statist.ical ~

bases for future consideration of snubber service life. "'-

-g 3/4.7.11 SEALED SOURCE CONTAMINATION

_ The limitations on removable contamination.for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for

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