Text

Amends 56 & 37 to Licenses NPF-9 & NPF-17,respectively, Changing Tech Specs to Increase Number of Operable & Operating Reactor Coolant Loops for Operation in Hot Standby Mode
	ML20203P692
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/28/1986
From:	Youngblood B; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20203P693	List: ML20203P692; ML20203P696;
References
	TAC-59696, TAC-59697, TAC-60710, TAC-60711, NUDOCS 8605080035
	Download: ML20203P692 (16)
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UNITED STATES g

NUCLEAR REGULATORY COMMISSION 3

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wAsHWOTON, D. C. 20066

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DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. NPF-9 1.

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

A.

The applications for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility O Power Company (licensee) perating License No. NPF-9 filed by the Duke dated January 10, 1986, and September 6, 1985, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.

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

Ther reasonable assurance (1) that the activities authorized by thi idment can be conducted without endangering the health and sa.

f the public, and (ii) that such activities will be conducted in compiance with the Comission's regulations set forth in 10 CFR Chapter I; D.

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

~I 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

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satisfied.

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-9 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.56, are hereby incorporated into the license.

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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 o

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B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A

Attachment:

Technical Specification Changes Date of Issuance: April 28, 1986 4

4 i

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r-i 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

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B. J. Youngblood, Director l'WR Project Directorate #4

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Division of PWR Licensing-A

Attachment:

Technical Specification Changes Date of Issuance: April 28, 1986

SEE PREVIOUS CONCURRENCE

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UNITED STATES

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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-17

'1.

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

A.

The applications for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (licensee) dated January 10, 1986, and September 6,1985, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (1) 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 comon defense and security or to the health and safety of the public; 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.

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.37, are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGU' ATORY COMMISSION L

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8. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A

Attachment:

Appendix A Technical Specification Changes Date of Issuance: April 28, 1986 1

SEE PREVIOUS CONCURRENCE

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ATTACHMENT TO LICENSE AMENDMENT NO. 56 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 37 FACILITY 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 corresponding over-leaf pages are also provided to maintain document completeness.

Amended Overleaf Page g

3/4 3-20 3/4 3-24a 3/4 3-27 3/4 3-36 3/4 4-2 3/4 6-21 3/4 6-22 3/4 6-41 3/4 6-42 B 3/4 4-1 9

TABLE 3.3-3 (Continued) g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E

m s

MINIMUM i

c TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABL'E MODES ACTION m

s 5.

Turbine Trip &

g feedwater Isolation o.

m a.

Automatic Actuation 2

1 2

1, 2 21 Logic and Actuation Relay b.

Steam Generator 3/sta. gen.

2/sta. gen.

1, 2 15*

Water Level--

in any oper-in each oper-High-High ating sta gen.

ating sta. gen.

,s*

c.

Doghouse Water 3/ train /

2/ train /

1, 2 25*

T Level (Feedwater Doghouse Doghouse Doghouse 5

Isolation Only) 6.

Containment Pressure Control 8(4/ train) 4/ train 8

1,2,3,4 26 System I

tt an IF i

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ACTION 25 - With one of the two trains of doghouse water level instrumenta-tion inoperable (less than the minimum required number of channels operable), restore the inoperable train to operable status in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . After 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months with one train inoperable, or within one hour with 2 trains inoperable, monitor doghouse water level in the affected doghouse cont.inuously until both trains are restored to operable status.

ACTION 26 - With any of the eight channels inoperable, place the inoperable

. channel (s) in the start permissive mode within ene hour and apply the applicable action statement (Containment Spray - T.S. 3.6.2, Containment Air Return / Hydrogen Skimmer - T.S. 3.6.5.6).

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MCGUIRE - UNITS 1 & 2 3/4 3-24a Amendment No.5dUnit 1)

Amendment No.3XUnit 2) 4

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l TABLE 3.3-4 (Continued)

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ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 1

A FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES E

q 4.

Steam Line Isolation vi w

a.

Manual Initiation N.A.

N.A.

i b.

Automatic Actuation Logic M.A.

N.A.

and Actuation Relays ro c.

Cantainment Pressure--High-High 1 2.9 psig 1 3.0 psig d.

Negative Steam Line 1 -100 psi /sec 5 -120 psi /sec j

Pressure Rate - High j

e.

Steam Line Pressure - Low 1 585 psig 1 565 psig 5.

Turbine Trip and Feedwater Isolation a.

Automatic Actuation Logic N.A.

N.A.

i and Actuation Relays b.

Steam Generator Water level--

< 82% of narrow range

< 83% of narrow range High-High (P-14)

Tnstrument span each steam Instrument span each steam

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generator generator ss 6.

Containment Pressure Control System i

tt Start Permissive / Termination 0.3 $ SP/T 1 0.4 PSIG 0.25 1 SP/T 1 0.45 PSIG s=

(SP/T)

EE t:X 22

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TABLE 4.3-2 (Continued)

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ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE,REQUIRENENTS TRIP g

ANALOG ACTUATING MDDES q

CHANNEL DEVICE MASTER SLAVE FOR WHICH un CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE H

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED i

4. Steam Line Isolation m

i a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3 d

1 b.

Automatic Actuatidh N.A.

N.A.

M(1)

Q 1,2,3 Logic and Actuation Relays 4

c.

Containment Pressure-- S R

M N.A.

N.A.

1, 2, 3

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High-High m

A d.

Negative Steam Line S

R M

N.A.

3 l

Pressure Rate-High

(

e.

Steam Line S

R M

N.A.

1, 2, 3 a

Pressure--Low i

5. Turbine Trip and Feedwater Isolation i

a.

Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2 i

Logic and Actuation j

kk Relay

g' i

g b.

Steam Generator Water S R

M N.A.

N.A.

1, 2 i

,g Level-High-High (P-14) l

((

6. Containment Pressure Control System j

Start Permissive /

S R

M N.A.

N.A.

1, 2, 3, 4 gg Termination hh

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d HOT STANDBY j

LIMITING CONDITION FOR OPERATION j

3.4.1.2 At least three of the reactor coolant loops listed below shall be OPERABLE and at least two of these reactor coolant loops shall be 4n operation:*

a.

Reactor Coolant Loop A and its associated steam generator and reactor coolant pump, b.

Reactor Coolant Loop 8 and its associated steam generator and reactor coolant pump, c.

Reacto-Coolant Loop C and its associated steam generator and reactor coolant pump, and d.

Reactor Coolant Loop D and its associated steam generator and reactor coolant pump.

APPLICABILITY: MODE 3 I

ACTION:

)

a.

With less than the above required reactor coolant loops OPERABLE, L

restore the required loops to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be

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in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

F b.

With only one reactor coolant loop in operation, restore at least two loops to operation within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or open the Reactor Trip System breakers, c.

With no reactor coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required reactor coolant loop to operation.

l SURVEILLANCE REQUIREMENTS i.

l 4.4.1.2.1 At least the above required reactor coolant pumps, if not in operation, shall be determined OPERABLE once per 7 days by verifying correct breaker alignments and indicated power availability.

4.4.1.2.2 The required steam generators shall be determined OPERA 8LE by verifying secondary side water level to be greater than or equal to 12% at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4.4.1.2.3 At least one reactor coolant loop shall be verified in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

"All reactor coolant pumps may be de-energized for up to I hour provided:

(1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is maintained at least 10*F below saturation temperature.

i McGUIRE - UNITS 1 and 2 3/4 4-2 Amendment No.56 (Unit 1)

Amendment No.37 (Unit 2) i-

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CONTAINMENT SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) 3)

Verifying that the Containment Pressure Control System func-i tions within the setpoint limits specified in Table 3.3-4, j

Item 6.

d.-

At least once per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle is unobstructed.

4 McGUIRE - UNITS 1 and 2 3/4 6-21 Amendment No. 56 (Unit 1)

Amendment No. 37 (Unit 2)

=. -. - -. -

CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION NbVES J

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LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves specified in Table 3.6-2 shall be OPERABLE with isolation times as shown in Table 3.6-2.

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

ACTION:

With one or more of the isolation valve (s) specified in Table 3.6-2 inoperable, maintain at least one isolation 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or b.

Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least

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one deactivated automatic valve secured in the isolation position, or c.

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

Be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

4 SURVEILLANCE REQUIREMENTS 4.6.3.1 The isolation valves specified in Table 3.6-2 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit h/ performance of a cycling test and verification of isolation time.

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l McGUIRE - UNITS 1 and 2 3/4 6-22

CONTAINMENT SYSTEMS

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i CONTAINMENT AIR RETURN AND HYDROGEN SKIP 94ER SYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.6 Two independent Containment Air Return and Hydrogen Skimmer Systems shall be OPERABLE.

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

ACTION:

With one Containment Air Return and Hydrogen Skimmer System inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS I

^

~

4.6.5.6.1 Each Containment Air Return and Hydrogen Skimmer System shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by:

Verifying that the air return and hydroge skimmer fans start a.

automatically on a Contaiheent Phase 8 Isolation (S ) test signal after a 9 i 1 cinute delay and operate for at leastp15 minutes; b.

Verifying that during air return fan operation with the air return i

fan damper closed and with the bypass dampers open, the fan motor current is less than or equal to 32 amps when the fan speed is 8701 30 rps; Verifying that with the hydrogen skimmer fan operating and the motor c.

operated valve in its suction line closed, the fan motor current is less than or equal to 21.5 amps when the fan speed is 3599 1 20 rpm; d.

Verifying that with the air return fan off, the motor operated damper in the air return fan discharge line to the containment's lower compartment opens automatically with a 10 + 1 second delay after a Containment Phase B Isolation (S ) test signal; p

Verifying that with the air return fan operating, the check damper e.

in the air return fan discharge line to the containment's lower compartment is open; f.

Verifying that the motor operated valve in the hydrogen skimmer suction line opens automatically and the hydrogen skimmer fans receive a start permissive signal; and i

g.

Verifying that with the fan off, the return air fan check damper is closed.

4.6.5.6.2 At least once per 18 months, each Containment Air Return and Hydrogen Skimmer System shall be demonstrated OPERABLE by verifying that the containment pressure control system functions within the setpoint limits specified in Table 3.3-4, Item 6.

Amendment No. 56(Unit 2)

McGUIRE - UNITS 1 and 2 3/4 6-41 Amendment No. 37(Unit 1)

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CONTAINMENT SYSTEMS

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FLOOR ORAINS f

~-w LIMITING CONDITION FOR OPERATION 3.6.5.7 The ice condenser floor drains shall be OPERABLE.

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

ACTION:

With the ice " condenser floor drain inoperable, restore the floor drain to i

OPERABLE status prior to increasing the Reactor Coolant System temperature above 200'F.

j me-SURVEILLANCE REQUIREMENTS 4.6.5.7 Each ice condenser floor drain shall be demonstrated OPERABLE at least once per 18 months during shutdown by:

a.

Verifying that valve gate opening is not impaired by ice, frost or

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debris,

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b.

Verifying that the valve seat is not damaged, c.

Verifying that the valve gate opens when a force of less than or equal to 66 lbs is applied, and Verifying that the drain line from the ice condenser floor to the d.

g containment lower compartment is unrestricted.

4 i

l-McGUIRE - UNITS 1 and 2 3/4 6-42 i

3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation and maintain DNBR above the design limit during all normal operations and antici-pated transients.

In MODES I and 2 with one reactor coolant loop not in oper-ation this specification requires that the plant be in at least HOT STANDBY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

In MODE 3, two reactor coolant loops provide sufficient heat. removal l

capability for removing decay heat; however, single failure considerations

. require that three loops be OPERABLE.

I In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either RHR or RCS) be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two RHR loops be OPERABLE.

The operation of one reactor coolant pump (RCP) or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual i

reactivity changes during boron concentratinn reductions in the Reactor Coolant System. The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.

s The restrictions on starting a reactor coolant pump with one or more RCS cold legs less than or equal to 300*F are provided to prevent RCS pressure transients, caused by energy additions from the Secondary Coolant System, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will i

be protected against overpressure transients and will not exceed the limits i

of Appendix G by either:

(1) restricting the water volume in the pressurizer j

and thereby providing a volume for the reactor coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water tempera-i ture of each steam generator is less than 50*F above each of the RCS cold leg l

temperatures.

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Amendment No.5d(Unit 1)

McGUIRE - UNITS 1 and 2 B 3/4 4-1 Amendment No.37(Unit 2)

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v t e Letter Sequence Other
TAC:59696, (Open) TAC:59697, (Open) TAC:60710, (Open) TAC:60711, (Open)
Initiation Request, Request, Request Acceptance... Administration Questions Answers Results Approval Other: ML20203P692
MONTHYEAR1986-01-28 [Table View]

ML20203P692

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