ML20245H928

Amends 94 & 76 to Licenses NPF-9 & NPF-17,respectively, Changing Tech Specs by Deleting Tables of Containment Penetration & Isolation Valves Incorporated Into FSAR

ML20245H928
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/28/1989
From:	Matthews D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245H931	List: ML20245H928 ML20245H933
References
NUDOCS 8905030583
Download: ML20245H928 (28)

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION 5

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DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. NPF-9 1.

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

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

Unit 1 by the Duke Power Company (the licensee) dated May 14,1986, as supplemented November 21, 1986 anci revised April 25, 1988 and April 5,1989, complies with the standards and requirements of the Atomic r

Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Ac.t, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and H

safety of the public, and (ii) that such activities will be conducted in compliance with the Comissic<n's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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 Commission'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 thiy license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appentiix A, as revised through Amendment No. 94, are hereby incorporated into the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION M

David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation i

Attachnent:

Technical Specification Changes Date of Issuance: April 28,1989 i

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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,

- and.. Paragraph 2.C.(2) of Facility Operating' License No. NPF-9 is hereby l

l amended to read as follows:

-(2). Technical Specifications I

The Technical Specifications contained in Appendix A, as revised.

i through Amendment No. 94, are hereby incorporated into the license, i

The licensee shall operate the facility in accordance with the

-Technical Specifications and the Environmental Protection Plan.

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. 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, " Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation-

Attachment:

Technical Specification Changes Date of Issuance:

April 28,1989 i

0FFICIAL RECORD COPY DSH LA-11-3 PM:PDII-3 DES SPLB 0 B 00 0 I-

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NUCLEAR REGULATORY COMMISSION o

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j WALHINGTON, D. C. 20555

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DUKE POWER COMPANY DOCKET N0. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. NPF-17 1.

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

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

Unit 2 by the Duke Power Company (the licensee) dated May 14, 1986, as supplemented November 21, 1986 and revised April 25, 1988, and April 5,1989, complies with the standards and requirements of the-Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and i

safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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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, 1 2.

. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

76, are hereby incorporated into the license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

April 28,1989 1

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2.

. Accordingly,.the. license.is hereby amended by. page changes, to the Technical t

. Specifications as indicated.in the attachments to this license amendment,.

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

)

(2). Technical Specifications The-Technical Specifications contained in Appendix _A, as revised through Amendnwnt No. 76., are hereby incorporated into the license.

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

3.

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

FOR THE NUCLEARLREGULATORY COMMISSION

_S David B..Matthews, Director Project Directorate II-3:

i Division of: Reactor Projects-I/II.

Office of Nuclear Reactor Regulation Atta' chnent:.

Technical Specification Changes Date of Issuance:

April 28,1989 i

0FFICIAL RECORD COPY L

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ATTACHMENT TO LICENSE AMENDMENT NO. 94 l

FACILITY OPERATING LICENSE NO. NPF-9 i

DOCKET NO. 50-369 AND l

TO LICENSE AMENDMENT NO. 76 FAC!LITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of.the Appendix "A" Technical Specifications with-the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

The related overleaf page is provided to maintain document completeness.

Amended Page Overleaf Page 1-2 3/4 6-1 3/4 6-2 3/4 6-5 3/4 6-6 3/4 6-7 3/4 6-8 3/4 6-9 3/4 6-9a 3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-25 3/4 6-26 3/4 6-27 3/4 6-28 3/4 6-29 3/4 6-30 B 3/4 6-4 8 3/4 6-3

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS l

3/4.6.1-PRIMARY CONTAINMENT

. Containment' Integrity..................................... '3/4 6-1 Containment Leakage......................................

3/4 6-2 b

' Containment Air Locks.....................................

3/4 6-10 Internal Pressure.........................................

3/4 6-12 l

Air Temperature......................

3/4 6-13 Containment Vessel Structural Integrity...................

3/4 6-14 Reactor Building. Structural Integrity.....................

3/4 6-15 Annulus. Ventilation System................................

3/4 6-16 Containment Ventilation System...........................

3/4 6-18 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System..................................

3/4 6-20 3/4.6.3 CONTAINMENT ISOLATION VALVES..............................

3/4 6-22 l

3/4 6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors.........................

3/4 6-31 Electric Hydrogen Recombiners.............................

3/4 6-32 Hydrogen Control Distributed Ignition System..............

3/4 6-33 l

3/4.6.5 ICE CONDENSER Ice Bed....................................................

3/4 6-34 i

.McGUIRE - UNITS 1 and 2 X

Amendment No. 94 (Unit 1)

Amendment No. 76 (Unit 2)

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' DEFINITIONS CONTAINMENT INTEGRITY

1. 7 CONTAINMENT INTEGRITY shall exist when:

a.'

All penetrations required to be closed during accident conditions are either:

1)

Capable of being closed by an-0PERABLE containment automatic isolation valve system, or operator action during periods when containment isolation valves may be opened under administrative-controls pursuant to Specification 4.6.1.1.a; or 2)

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions.

b.

All equipment hatches are closed and sealed, c.

Each air. lock is in compliance with.the requirements of Specification 3.6.1.3, I

'd.

.The containment leakage rates are within the limits of Specification 3.6.1.2, and e.-

The sealing mechanism associated with each penetration (e.g., welds, bellows, or 0 rings) is OPERABLE.

CONTROLLED LEAKAGE 1.8. CONTROLLED LEAKAGE shall be that seal water flow supplied to the reactor coolant' pump seals.

j CORE ALTERATION 1.9 CORE ALTERATION-shall be the movement or manipulation of any component-within the reacter pressure vessel with the vessel head removed and fuel in the vessel.

Suspension of CORE ALTERATION shall not preclude completion of

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movement of a component to a safe conservative ' position.

l DOSE EQUIVALENT I-131

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1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, 1-134, and I-135 actually present.' The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."

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E - AVERAGE DISINTEGRATION ENERGY i

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1.11 E shall be the average (weighted in proportion to the concentration of j

each. radionuclides in the sample) of the sum of the average beta and gamma energies per disintegration (MeV/d) for the radionuclides in the sample.

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l McGUIRE - UNITS 1 and 2 1-2 Amendment No. 76 (Unit 2)

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Amendment No. 94 (Unit 1) j

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/4.6 CONTAINMENT SYSTEMS l

3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION

3. 6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY:

MODES 1, 2, 3, and 4.

j ACTION:

' Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within'the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated a.

At least once per 31 days by verifying that all penetrations

• not capable of being closed by 0PERABLE containment automatic isolation valves or operator action during periods when containment isolation valves are open under. administrative control,** and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions; b.

By verifying that each containment air lock is in compliance with Specification 3.6.1.3; and c.

After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following a Type A or B test, by 7eak rate testing the seal.with gas at P,these seals is, 14.8 psig, and verifying that when the measured leakage rate for added to t,he leakage rates determined pursuant to Specification 4.6.1.2d.

for all other Type B and C penetrations, the combined leakage rate is less than.0.60 L

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Except valves, blind flanges, and deactivated automatic valves which are

' located inside the containment and the annulus and are locked, sealed or otherwise secured in the closed position.

These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be

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performed more often than once per 92 days.

• • The following valves may be opened on an intermittent basis under administrative control:

NC-141, NC-142, WE-13, WE-23, VX-34, VX-40, FW-11, FW-13, FW-4.

McGUIRE - UNITS 1 and 2 3/4 6-1 Amendment No. 94 Amendment No. 76 (Unit 1)

(Unit 2)

4 CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a.

An overall integrated leakage rate of:

1)

Less than or equal to L 0.30% Sy weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,a,4.8 psig, or 1

a 2)

Less than or equal to L, 0.14% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a rbduced pressure of P, 7.4 psig.

t b.

A combined leakage rate of less than 0.60 L for all penetrations and valves subject to Type B and C tests, wflen pressurized to P '

and a

l c.

A combined bypass leakage rate of less than 0.07 L for all penetrations identified as secondary containment bfpass leakage l

paths when pressurized to P '

a APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With (a) the measured overall integrated containment leakage rate exceeding 0.75 L or 0.75 L as applicable, or (b) the measured combined leakage rate f8r all penekr,ations and valves subject to Types B and C tests exceeding 0.60 L, or (c) the combined bypass leakage rate exceeding 0.07 L restor 8 the overall integrated leakage rate to less than 0.75 L 8rlessthan or equal to 0.75 L, as applicable, and the combined leakage rafe for all penetrationsandvklvessubjecttoTypeBandCteststolessthan0.60L' a

and the combined bypass leakage rate to less than 0.07 L prior to increasingtheReactorCoolantSystemtemperatureabove300F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 or the mass plot method:

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l McGUIRE - UNITS 1 and 2 3/4 6-2 Amendment No.94 (Unit 1)

Amendment No.76. (Unit 2)

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. CONTAINMENT SYSTEMS-3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolction valves shall be OPERABLE with isolation times

. less than or equal. to the required isolation times.

1 APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one or more isolation valve (s) inoperable, maintain at least one isolation l

valve OPERABLE in each affected penetration that is open and:

a.

Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.

Isolete each affected' penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least j

one-deactivated automatic valve secured in the isolation position, i

or c.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

.l SURVEILLANCE REQUIREMENTS i

i 4.6.3.1 Each isolation valve shall be demonstrated OPERABLE prior to returning l

the valve to service after maintenance, repair or replacement work is performed on the valve or its. associated actuctor, control or power circuit by performance of a cycling test and verification of isolation time.

McGUIRE - UNITS 1 and 2 3/4 6-22 Amendment No. 94 (Unit 1)

Amendment No. 76 (Unit 2) i

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CONTAINMENT SYSTEMS 1

SURVEILLANCE' REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve shall be demonstrated OPERABLE during the COLD l

- SHUTDOWN or REFUELING MODE at least once per 18 months by:

Verifying that on a Phase A Containment Isolation test signal, each a.

Phase A isolation valve actuates to its isolation position, b.

-Verifying that.on a_ Phase B Containment Isolation test signal, each Phase.B isolation valve actuates to its isolation position, and

.. Verifying that on a Containment Radioactivity-High test signal, each 1

purge and exhaust valve-actuates to its isolation position.

4.6.3.3 The-isolation time of each power operated or automatic valve shall be l

determined to be within its limit when tested pursuant to Specification 4.0.5.

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4 CONTAINMENT SYSTEMS BASES 3/4.6.1.7 REACTOR BUILDING STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment reactor building will be maintained comparable to the original design standards for the life of the facility.

Structural integrity is required to provide.

r (1) protection for the steel vessel from external missiles, (2) radiation shielding in the event of a LOCA, and (3) an annulus surrounding the steel

.)

vessel that can be maintained at a negative pressure during accident condi-1 tions.

A visual. inspection is sufficient to demonstrate this capability.

l 3/4.6.1.8 ANNULUS VENTILATION SYSTEM The OPERABILITY of the Annulus Ventilation System ensures that during i

LOCA conditions', containment vessel leakage into the annulus will be filtered 1

through the HEPA filters and charcoal adsorber trains prior to discharge to the atmosphere.

Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

This requirement is necessary to meet the assumptions.used in the accident analyses and limit the SITE BOUNDARY radiation doses to within the dose guideline values of 10 CFR Part 100 during LOCA conditions.

ANSI N510-1975 will be used as a procedural guide for surveillance i

testing.

3/4.6.1.9 CONTAINMENT VENTILATION SYSTEM l

The containment purge supply and exhaust isolation valves for the lower compartment (24-inch) and instrument room (12-inch and 24-inch) are required to be sealed closed during plant operations since these valves have not been demonstrated capable of closing during a LOCA.

Maintaining these valves sealed closed during plant operation ensures that excessive quantities of radioactive material will not be released via the Containment Purge System.

To provide assurance that these containment valves cannot be inadvertently opened, the valves'are sealed closed in accordance with Standard Review Plan 6.2.4 which includes mechanical devices to seal or ' lock the valve closed, or prevents power from being supplied to the valve operator.

The use of the containment purge lines is restricted to the purge supply and exhaust isolation valves in the upper compartment (24-inch) since, unlike the valves in the lower compartment and instrument room, the upper compartment valves will close during a LOCA.

Therefore, the SITE BOUNDARY dose guideline values of 10 CFR Part 100 would not be exceeded in the event of an accident during containment purging operation.

Operation with these valves open will be limited to 250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> during a calendar year.

Leakage integrity tests with a maximum allowable leakage rate for containment purge supply and exhaust supply valves will provide early indica-tion of resilient material seal degradation and will allow opportunity for j

repair before gross leakage failures could develop.

The 0.60 L leakage limit ofSpecification3.6.1.2b.shallnotbeexceededwhentheleakaheratesdeter-mined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.

McGUIRE - UNITS 1 and 2 B 3/4 6-3

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o CONTAINMENT' SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM

-The OPERABILITY of the Containment Spray System ensures that containment i

depressurization and cooling capability will be available in the event of a LOCA.

The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.

3/4.6.3 CONTAINMENT ISOLATION VALVES

.The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the retui ements of GDC 54 thru 57 of Appendix A to 10 CFR Part 50.

Containment isc

%n within the time limits specified for those isolation valves designed to

• 9 automatically ensures that the release of radioactive material L environment will be consistent with the assumptions used in the ane-

.s for a LOCA.

Containment isolation valves are listed in FSAR Table 6.2.4-1.

'Those valves with a required isolation time have a value given in the " MAX ISOLATION TIME-(SEC)" column.

Penetration test type (type B, type C, or None) is listed in the " TEST TYPE" column of the table for each containment penetration.

Changes to the FSAR are made in accordance with 10 CFR 50.59.

3/4.6.4 COMBUSTIBLE GAS CONTROL

-The OPERABILITY of the equipment and systems required for the detection i

and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions, Either recombiner unit is capable of controlling the expected hydrogen' generation associated with:

(1) zirconium-water reactions, (2) radiolytic decomposition of water, and (3) corrosion of

(

matals within containment.

These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA", March 1971.

The OPERABILITY of at least 64 of 66 igniters ensures that the Distributed Ignition System will maintain an effective coverage throughout the containment.

This system of igniters will initiate combustion of any significant amount of hydrogen released after a degraded core accident.

This system is to ensure burning in a controlled manner as the hydrogen is released instead of allowing it to be ignited at high concentrations by a random ignition source.

I McGUIRE - UNITS 1 and 2 B 3/4 6-4 Amendment No.94 (Unit 1)

Amendment No. 76 (Unit 2)

_.