ML20199J094

Discusses Plant,Unit 3 Rev to TS Bases,Section 3/4.5.2.Encl TS Pages Should Be Inserted Into TS to Ensure That NRC Staff & NNECO Have Identical TS Bases Pages

ML20199J094
Person / Time
Site:	Millstone
Issue date:	01/21/1999
From:	Andersen J NRC (Affiliation Not Assigned)
To:	Bowling M, Loftus P NORTHEAST NUCLEAR ENERGY CO.
References
TAC-MA4424, NUDOCS 9901260057
Download: ML20199J094 (7)

Text

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, , January 21, 1999  ;

Mr. M:rtin L. Bowling, Jr.

Recovery Officer - Technical Services Northeast Nuclear Energy Company c/o Ms. Patricia A. Loftus l Director- Regulatory Affairs P. O. Box 128 Waterford, CT 06385

SUBJECT:

MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - REVISION TO TECHNICAL SPECIFICATIONS BASES (TAC NO. MA4424) )

Dear Mr. Bowling:

l I

By letter dated December 21,1998, Northeast Nuclear Energy Company (NNECO) provided l the NRC with changes to Technical Specifications (TS) Bases Section 3/4.5.2. NNECO provided the TS Bases page to the NRC for information only.

)

As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. Changes to the TS Bases may voluntarily be made in accordance with the provisions of 10 CFR 50.59.

Should the proposed change involve an unreviewed safety question pursuant to 10 CFR l

50.59(a)(2), or involve a change in the interpretation of implementation of the TS (i.e.,

constitute a TS change), then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.

The TS Bases you provided are hereby retumed to you and should be inserted in the TS to ensure the NRC staff and NNECO have identical TS Bases pages. The staff did not perform an evaluation of your TS Bases revisions and staff concurrence with the revisions is not

implied by this letter. The staff may review the evaluations that support these TS Bases revisions during the next inspection of Millstone Unit 3's implementation of 10 CFR 50.59, i

Sincerely, i

/s/  !

James W. Andersen, Project Manager g 2IOO$ $0 h 23 Project Directorate 1-2 p PDR Division of Reaction Projects - 1/11 Office of Nuclear Reactor Regulation Docket No. 50-423

Enclosure:

Bases pages /

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.. - . . . . . - . - . - - . _ . - . _ _ _ _ _ _ _ . ~ ~ - . . - - . - -

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[ t p UNITED STATES I

,, s j- NUCLEAR REGULATORY COMMISSION I 2 WASHINGTON, D.C. 30006 4 001 -

y j' Danuary 21, 1999 Mr. Martin L. Bowling, Jr.

Recovery Officer - Technical Services {

j . Northeast Nuclear Energy Company  ;

c/o Ms. Patricia A. Loftus Director- Regulatory Affairs ,

P. O. Box 128 Waterford, CT 06385 '

i

SUBJECT:

MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 - REVISION TO 1

TECHNICAL SPECIFICATIONS BASES (TAC NO. MA4424) l l

Dear Mr. Bowling:

By letter dated December 21,1998, Northeast Nuclear Energy Company (NNECO) provided the NRC with changes to Technical Specifications (TS) Bases Section 3/4.5.2. NNECO l provided the TS Bases page to the NRC for information only.

l l

As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. Changes I to the TS Bases may voluntarily be made in accordance with the provisions of 10 CFR 50.59.

Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change in the interpretation of implementation of the TS (i.e.,

l constitute a TS change), then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.

l

! The TS Bases you provided are hereby retumed to you and should be inserted in the TS to ensure the NRC staff and NNECO have identical TS Bases pages. The staff did not perform an evaluation of your TS Bases revisions and staff concurrence with the revisions is not implied by this letter. The staff may review the evaluations that support these TS Bases revisions during the next inspection of Millstone Unit 3's implementation of 10 CFR 50.59.

Sincerely, t

b a .s W. Andersen, Project Manager roject Directorate 1-2 Division of Reaction Projects - 1/II  ;

Office of Nuclear Reactor Regulation

.l l Docket No. 50-423 1

Enclosure:

Bases pages cc w/ encl: See next page I i

• Millston3 Nucirr Power Stati:n Unit 3 l cc:

l Lillian M. Cuoco, Esquire Mr. F. C. Rothen i Senior Nuclear Counsel Vice President - Nuclear Work Services Northeast Utilities Service Company Northeast Utilities Service Company P. O. Box 270 P. O. Box 128 l Hartford, CT 06141-0270 Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D. Ernest C. Hadley, Esquire Director, Division of Radiation 1040 B Main Street Department of Environmental Protection P.O. Box 549

, 79 Elm Street West Wareham, MA 02576 Hartford, CT 06106-5127 Mr. John Buckingham Regional Administrator, Region 1 Department of Public Utility Control U.S. Nuclear Regulatory Commission Electric Unit 475 Allendale Road 10 Liberty Square King of Prussia, PA 19406 New Britain, CT 06051 First Selectmen Mr. James S. Robinson, Manager Town of Waterford Nuclear investments and Administration 15 Rope Ferry Road New England Power Company Waterford, CT 06385 25 Research Drive Westborough, MA 01582 Mr. Wayne D. Lanning, Director Millstone inspections Mr. Raymond P. Necci Office of the Regional Administrator Vice President - Nuclear Oversight and 475 Allendale Road Regulatory Affairs King of Prussia, PA 19406-1415 Northeast Utilities Service Company P. O. Box 128 Mr. M. H. Brothers Waterford, CT 06385 Vice President - Millstone Operations Northeast Nuclear Energy Company Deborah Katz, President P.O. Box 128 Citizens Awareness Network Waterford, CT 06385 P.O. Box 83 Shelbume Falls, MA 03170 Mr. M. R. Scully, Executive Director Connecticut Municipal Electric Mr. Allan Johanson, Assistant Director Energy Cooperative Office of Policy and Management 30 Stott Avenue Policy Development and Planning Norwich, CT 06360 Division 450 Capitol Avenue - MS# 52ERN Mr. John Carlin P. O. Box 341441 Vice President - Human Services Hartford, CT 06134-1441 Northeast Utilities Service Company P. O. Box 128 Waterford, CT 06385

Millstone Nuclear Power Station Unit 3 cc:

The Honorable Terry Concannon Citizens Regulatory Commission Nuclear Energy Advisory Council ATTN: Ms. Susan Perry Luxton Room 4035 180 Great Neck Road Legislative Office Building Waterford, CT 06385 Capitol Avenue Hartford, CT 06106 Mr. William D. Meinert Nuclear Engineer Mr. Evan W. Woollacott Massachusetts Municipal Wholesale Co-Chair E ectric Company Nuclear Energy Advisory Council P.O. Box 426 128 Terry's Plain Road Ludlow, MA 01056 Simsbury, CT 06070 Mr. John W. Beck, President Little Harbor Consultants, Inc.

Millstone -ITPOP Project Office P.O. Box 0630 Niantic, CT 06357-0630 Mr. Leon J. Olivier Chief Nuclear Officer- Millstone N)rtheast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385 Mr. Daniel L. Curry Project Director Parsons Power Group Inc.

2675 Morgantown Road Reading, PA 19607 Mr. Chris Schwarz Director- Unit 3 Northeast Nuclear Energy Company P.O. Box 128 Waterford, CT 06385 5

Senior Resident inspector '

Millstone Nuclear Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 Nicholas J. Scobbo, Jr., Esquire Ferriter, Scobbo, Caruso, & Rodophele, P.C.

75 State Street,7th Floor Boston, MA 0210

i REVISED TECHNICAL SPECIFICATIONS BASES FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Appendix A, Technical Specifications Bases, with the attached page3. The revised pages contains verticallines indicating the areas of change.

Remove jaggi B 3/4 5-2 8 3/4 5-2 B 3/4 5-2a

I EMERGENCY CORE COOLING SYSTEMS BASES ECCS SUBSYSTEMS (Continued)

The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. Surveillance i Requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow i from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and  !

i (3) provide an acceptable level of total ECCS flow to all injection points l equal to or above that assumed in the ECCS-LOCA analyses.

is fullSurveillance of water. Requirement 4.5.2.b.1 requires verifying that the ECCS piping The ECCS pumps are normally in a standby, nono with the exception of the operating centrifugal charging pump (s).perating As such, mode, the ECCS flow path piping has the potential to develop voids and pockets of entrained gases. Maintaining the piping from the ECCS pumps to the RCS full of water ensures that the system will perform properly when required to inject into the l

i RCS. This will also prevent water hammer, pump cavitation, and pumping of noncondensible gases (e.g., air, nitrogen, or hydrogen) into the reactor vessel following an SI signal or during shutdown cooling.

, This Surveillance Requirement is met by:

ventingECCSpumpcasingsandtheaccessibledischargepipihg'highpoints - - - - - -

including the ECCS pump suction crossover piping (i.e., downstream of valves 3RSS*MV8837A/B and 3RSS*MV8838A/B to safety injection and charging pump suction).

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venting of the nonoperating centrifugal charging pumps at the suction line test connection. The nonoperating centrifugal charging pumps do not have casing vent connections and venting the suction pipe will assure that the pump casing does not contain voids and pockets of entrained gases.

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l using an external water level detection method for the water filled portions of RSS piping upstream of valves 3RSS*MV8837A/B and 3RSS*MV8838A/B, since venting would breach the containment pressure boundary. Alternatively and when deemed necessary by the external water level detection method, venting may be used after entering LCO action statement 3.6.2.2 and after establishing sufficiant head pressure.

The following ECCS subsections are exempt from this Surveillance:

the operating centrifugal charging pump (s) and associated piping - as an operating pump is self venting and cannot develop voids and pockets nf entrained gases.

i NILLSTONE - UNIT 3 8 3/4 5-2 Amendment No. Jpp, 0578 Revised by letter da#7, Jp7,21,1995 ted Jan.

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EMERGENCY CORE COOLING SYSTEMS

, RASES ECCS SUBSYSTEMS (Continued) the RSS pumps, since this equipment is laid-up dry during plant operation.

the RSS heat er. changers, since this equipment is laid-up dry during plant operation.

the RSS piping that is not maintained filled with water during plant operation.

I surveillance Requirement 4.5.2.C.2 requires that the visual inspection of the containment be performed at least once daily if the containment has been entered that day and when the final containment entry is made. This will reduce the number of unnecessary inspections and also reduce personnel exposure.

3/4 5.4 REFUELING WATER STORAGE TANK Tle OPERABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injec-tion by the ECCS in the event of a LOCA. The limits on RWST minimum volume and boron concentration ensure that: (1) sufficient water is available within containment to permit recirculation cooling flow to the core, and (2) the reactor will remain suberitical in the cold condition following mixing of the RWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analyses.

The contained water volume limit includes an allowance for water-not---  !

usable because of tank discharge line location or other physical characteristics.

The limits on contained water volume and boron concentration of the RWST  !

also ensure a pH value of between 7.0 and 7.5 for the solution recirculated within containment after a LOCA. This pH band minimizes the effect of chloride l and caustic stress corrosion on mechanical systems and components.

The maximunVainimum solution temperatures for the RWST in MODES 1, 2, 3 i and 4 are based on analysis assumptions.

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I MILLSTONE - UNIT 3 B 3/4 5-2a Amendment No. Jpp, JJ7 177, Revised by letter datedlaM1_19E

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