Text

Amends 82 & 63 to Licenses NPF-09 & NPF-17,respectively, Removing Obsolete Text Re Upper Head Injection Sys from Tech Specs
	ML20154C522
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/10/1988
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	;
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ML20154C524	List: ML20154C522;
References
	NUDOCS 8805180210
	Download: ML20154C522 (13)
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o UNITED STATES E'

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DUKE POWER COMDANY 00CKET NO. 50-369 ftcGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l

l Amendment No. 82 l

License No. NPF-9 i

i 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for anendment to the McGuire Nuclear Station Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated March 14, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Com.'ssion's rules and regulations as set forth in 10 CFR Chapter It B.

The facility will operate in confornity with the application, as anended, the provisions of the Act, and the rules and regulations of the Comissiont l

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, i

and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as fellows:

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The Technical Specifications contained in Appendix A, as revised through Amendment No. 82, are hereby incorporated into the license.

i The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, i

3.

This license amendment is effective as of its date of issuance.

FOR THE HUCLEAR REGULATORY C04tISSION Original signed by:

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Division of Reactor Projects-I/II

Attachment:

Technical Specification Changes Date of Issuance: May 10, 1988 J g (Fkh) w OGC-W PDIh3 AD

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DOCKET NO. 50-370 l

McGUIRE NUCLEAR STATION, UNIT 2 APENDMENT TO FACILITY OPERATING LICENSE I

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t Amendment No. 63 License No. NPF-17.

1.

The Nuclear Regulatory Comission (the Comission) has found that:

The app (lication for amendment to the McGuire Nuclear Station, A.

Unit 2 the facility) Facility Operating bytheDukePowerCompany(thelicensee)LicenseNo.NPF-17 filed dated March 14, 1988, complies with the standards and requirements of the Atomic Energy j

Act of 1954, as amended (the Act) and the Comission's rules and i

regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as I

amended, the provisions of the Act, and the rules and regulations of the Comission; e

i C.

There is reasonable assuranco (i) that the activities authorized by this amendnent can be conducted without endangering the health and j

safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter It

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D.

The issuance of this amendment will not be inimical to the common i

defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of i

the Comission's regulations and all applicable requirements have been satisfied, i

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2 i 2.

Accordingly, the license is hereby amended by page charces to the Technical Specifications as indicated in the attachments to this iicense amendment, i

and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised j

through Amendment No.

63, are hereby incorporated into the license, j

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendr.ent is effective as of its date of issuance.

FOR THE NUCLEAR REGt'LATORY COMMIS$10N Original signed by:

David B. Matthews. Director Project Directnrate 11-3 Division of Reactor Projects-l/II i

Attachment:

Techrical Specification Chances I

j Date of Issuance: May 10, 1988 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 82 FACILITY OPERATING LICENSE NO. NPF-9 1

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DOCKET NO. 50-369 s

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TO LICENSF AllENDMENT NO. 63 l

FACILITY OPEPATING LICENSE NO. NPF-17

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f DOCKET N0. 50-370 1

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Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number end j

contain vertical lities indicating the areas of change.

I Amended Pace I

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3/4 5-1 3/4 5 2a 3/4 5-2b 3/4 5-3 i

3/4 5-3a 3/4 5-3b 3/4 5-4 8 3/4 5-1

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i INDEX l

f LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS j

SECTION PAGE 3/4.4.9 PRESSURE / TEMPERATURE LIMITS I

i Reactor Coolant System.................

4 3/4 4-30 l

FIGURE 3.4-2a UNIT 1 REACTOR COOLANT SYSTEM i

HEATUP LIMITATIONS - APPLICABLE i

UP TO 10 EFPY.........................

3/4 4-31 FIGURE 3.4-2b UNIT 2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS-APPLICABLE UP TO 10 EFPY.........................

3/4 4-32 FIGURE 3.4-3a UNIT 1 REACTOR COOLANT SYSTEM l

COOLDOWN LIMITATIONS - APPLICABLE UP TO 10 EPFY............................

3/4 4-33 FIGURE ;.4-3b UNIT 2 REACTOR COOLANT SYSTEM i

C00LOOWN LIMITATIONS-APPLICABLE UP l

TO 10 EPFY............................

3/4 4-34 l

l TABLE 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM -

l WITHDRAWAL SCHEDULE....................e.............

3/4 4-35 j

Pressurizer...............................................

3/4 4-36 Overpressure Protection Systems...........................

3/4 4-37 3/4.4.10 STRUCTURAL INTEGRITY......................................

3/4 4-39 3/4.4.11 REACTOR VESSEL HEAD VENT SYSTEM...........................

3/4 4-40 3/4.5 EMZRGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS Cold Leg Injection........................................

3/4 5 1 (0eleted).................................................

3/4 5-3 3/4.5.2 ECCS SUBSYSTEMS - T,yg 1 350'F.............................

3/4 5-5 3/4.5.3 ECCS SUBSYSTEMS - T,yg $ 350*F.............................

3/4 5-9 3/4.5.4 (0eleted)..................................................

3/4.5-11 3/4.5.5 REFUELING WATER STORAGE TANK...............................

3/4 5-12 j

McGUIRE - UNITS 1 and 2 IX Amendment No. 82 (Unit 1)

Amendment No. 63 (Unit 2)

3/4.5 EMERGENCY CORE CCOLING SYSTEMS 3/4.5.1 ACCUMULATORS COLD LEG INJECTION LIMITING CONDITION FOR OPERATION 3.5.1.1 Each cold leg injection accumulator shall be OPERABLE with:

a.

The isolation valve open, b.

A contained borated water volume of between 6870 and 7342 gallons, c.

A boron concentration of between 1900 and 2100 pra, d.

A nitrogen cover pressure of between 585 and 639 psig, and e.

A water levol and pressure channel OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3*.

ACTION:

a.

With one accumulator inoperable, except as a result of a closed isolation valve or boron concentr6 tion less than 1900 ppm, restore the inoperable accumulator to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STAN0BY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , c.

With one accumulator inoperable due to baron concentration less than 1900 ppm and:

1)

The volume weighted average boron concentration of the three limiting accumulators 1900 ppm or greater, restore the in-operable accumulator to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the low boron determination or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2)

The volume weighted average boron concentration of the three limiting accumulators less than 1900 ppe but greater than 1500 ppm, restore the inoperable accumulator to OPERABLE status or return the volume weighted average boron concentration of the three limiting accumulators to greater than 1900 ppm and enter ACTION c.1 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the low boron determinstion or be in HOT STAN0BY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce pressurizer pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Pressurizer pressure above 1000 psig.

McGUIRE - Vi4ITS 1 and 2 3/4 5-1 Amenoment No. 82 (Unit 1)

Amerhnt No. 63 (Unit 2)

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1 McGUIRE - UN!TS 1 and 2 3/4 5-24 Amendment No 82 (Unit 1)

Amendment No 63 (Unit 2)

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4 Pages 3/4 5-3, 3/4 5-3a, and 3/4 5-3b intentionally deleted.

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McGUIRE - UNITS 1 and 2 3/4 5-3 Amendment No.82 (Unit 1)

Amendment No.63 (Unit 2) i

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t McGUIRE - UNITS ~. and 2 3/4 5-4 Amendment No. 82 (Unit 1)

Amendment No. 63 (Unit 2) 4

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3/4.5 EMERGENCY CORE COOLING SYSTEMS BASES 3/4.5.1 ACCUMULATORS The OPERABILITY of each Reactor Coolant System (RCS) Cold Leg Accumulator ensures that a sufficient volume of borated water will be immediately forced into the reactor core through each of the cold legs in the event the RCS pre.s-sure falls below the pressure of the accumulators.

This initial surge of water into the core provides the initial cooling mechanism during large RCS p*ge rup-tures.

The limits on accumulator volume, boron concentration and pref 5ure ensure that the assumptions used for accumulator injection in the safety analysis are met.

The allowed down time for the accumulators are variable based upon boron concentration to ensure that the reactor is shutdown following a LOCA and '. hat any problems are corrected in a timely manner.

Subcriticality is assured when baron concentration is above 1500 ppm, so additional down time is allowed when concentration is above 1500 ppm.

A concentration of less than 1900 ppm in any single accumulator or as a volume weighted average may be indicative of a pro-blem, such as valve leakage, but since reactor shutdown is assured, additional time is allowed to restore boron concentration in the accumulators.

The accumulator power operated isolation valves are considered to be "operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.

In addition, as these accumulator isolation valves fail to meet single failure criteria, removal of power to the valves is required.

The limits for operation with an accumulator inoperable for any reason ex-cept an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional accumulator which may result in unacceptable peak cladding temperatures.

If a closed isolation valve cannot be immediately opened, the full caoability of one accumulator is not available and prompt action is required to place the reactor in a mode where this capability is not required.

The original licensing bases of McGuire assumes both the UHI system and the Cold Leg Accumulators function to mitigate postulated accidents.

Subse-quent analyses, documented in "McGuire Nuclear Station, Safety Analysis for UHI Elimination" dated September 1985, and docketed by Duke letter dated October 2, 1985, support the determination that UHI is no longer required pro-vided the Cold Leg Accumulator volume is adjusted to be consistent with that assumed in the Safety Analysis.

McGUIRE - UNITS 1 and 2 B 3/4 5-1 Amendment No. 82 (Unit 1)

Amendment No. 63 (Unit 2)

c EMERGENCY CORE COOLING SYSTEMS BASES l

l 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS l

The OPERABILITY of two independent ECCS subsystems ensures that sufficient emergency core cooling capability will be available in the event of a LOCA assuming the loss of one subsystem through any single failure consideration.

Either subsystem operating in nnjunction with the accumulators is capable of supplying sufficient core coolnig to limit the peak cladding temperatures j

within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.

In addition, each ECCS subsystem provides long-term core cooling capability in the recirculation mode during the accident recovery period.

j With the RCS temperature below 350 F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.

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The limitation for a maximum of one centrifugal charging pump and one Safety Injection pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps and Safety Injection pumps except the required OPERABLE charging pump to be inoperable below 300 F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

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 sutaystem OPERABILITY is maintained.

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

3/4.5.4

[ Deleted) 3/4.5.5 REFUELING WATER STORAGE TANK The OPERABILITY of the refueling water storage tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection 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 subcritical in the cold condition following mixing of the RWST and the RCS water volumes with all control rods inserted except McGUIRE - UNITS 1 and 2 8 3/4 5-2 Amendment No.82 (Unit 1) l Amendment No.63 (Unit 2)

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EMERGENCY CORE COOLING SYSTEMS BASES REFUELING WATER STORAGE TANK (Continued) 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 8.5 and 10.5 for the solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

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i McGUIRE - UNITS 1 and 2 B 3/4 5-3 Amendment No. 82 (Unit 1) l Amendment No. 63 (Unit 2)

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ML20154C522

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