Text

Amends 29 & 10 to Licenses NPF-9 & NPF-17,respectively, Changing Tech Specs Re Response Time for Steamline Isolation,Deleting Mechanical Snubbers & Surveillance Requirements for Sprinkler Sys Valves
	ML20087C014
Person / Time
Site:	McGuire, Mcguire
Issue date:	02/29/1984
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20087C016	List: ML20087C014; ML20087C018;
References
	NUDOCS 8403120213
	Download: ML20087C014 (27)
	v • d • e

- _.

=

o sseg

/

o UNITED STATES g

[,'

3 y.. yg NUCLEAR REGULATORY COMMISSION W ASHING TON, D. C. 20555

\\, %...../

DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 29 j

License No. NPF-9 1.

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

A.

The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated August 2,1983, complies with the standards and requirenents 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 conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; 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 Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license amendment will not be inimical to the cor. mon 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 Conunission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Teshnical 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:

8403120213 840229 PDR ADOCK 05000369 P

PDR

2_

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.29, are hereby incorporated into this license.

The licensee shall operste the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

(/ (Et W

Elinor G. Adenstm, Chief Licensing Branch No. 4 Division of Licensing i

Attachment:

Technical Specification Changes Date of Isicance: February 29, 1984 4

9 4

l

o uct

/

0 UNITED STATES E**3sg g,

NUCLEAR REGULATORY COMMISSION

/ l WASHINGTON D. C. 20555

,,(. -l'. a.../

DUKE POWER COMPANY

~

DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 N4ENDMENT TO FACILITY OPERATING LICENSE Amendment No.10 License No. NPF-17 1.

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

A.

The application for amendment to the McGuire Nuclear Station, 'Jnit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Pcwer Company (licensee) dated August 2,1983, complies with the standards and requirements of the Atonic 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 conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance: (i) that the activitie" 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 license 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 accordan'ce 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 paragra;:h 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.10, are hereby incorporated into this license.

The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmantal Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing

Attachment:

Technical Specification Changes Date of Issuance: Feb ruary 29, 1984

]

J ATTACHMENT TO LICENSE AMENDMENT NO. 29 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMEN 0 MENT NO. 10 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 a vertical line indicating the area of change. The corresponding over-leaf pages are also provided to maintain document completeness.

Amended Overleaf Page 7 age 3/4 3-3 3/4 3-4 3/4 3-7 3/4 3-8 3/4 3-24 3/4 3-23 3/4 3-31

'3/4 3-32 3/4 3-77 3/4 3-78 3/4 4-30 3/4 A-29 3/4 7-27 3/4 7-28 3/4 7-35 3/4 7-36 3/4 7-38 3/4 7-37 3/4 7-42 3/4 7-41 3/4 10-2 3/4 10-1 O

G e

TABLE 3.3-1 (Continued)

?

Ej REACTORTRIPSYSTEMINST9UMENTAT[0N

o MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE si FUNC?l0NAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACT10N Z

m 8.

Overpower aT s

g Four Loop Operation 4

2 3

1, 2 6

Three Loap Operation

(**)

c' m

9.

Pressurizer Pressure-Low 4

2 3

1 6

10.

Pressurizer Pressure--High 4

2 3

1, 2 6

11.

Pressurizer Water Level--High 3

2 2

's 7

u,);

22.

Low Reactor Coolant Flow a.

Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1

7, u,

J, any oper-each oper-ating loop ating loop b.

Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1

7 below P-8) two oper-cach oper-ating loops ating loop 13.

Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2 6

g,9 Level--Low-Low in ;any oper-each oper-g[ g ating stm.

ating stm.

gg gen.

gen.

55 5E hsh;

^^c

-33

.r r

TABLE 3.3-1 (Continued)

Ng REACTOR TRIP SYSTEM INSTRUMENTATION MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE g

FUNCTIONAL UNIT OF CH?.NNELS TO TRIP OPERABLE MUDES ACTION m

v' 14.

Undervoltage-Reactor Coolant Pumps (above P-7) 4-1/ bus 2

3 1

6, 9a 15.

Underfrequency-Reactor Coolant g

Pumps (above P-7) 4-1/ bus 2

3 1

6 ro 16.

Turbine Trio a.

Low Fluid Oil Pressure 3

2 2

1 7

b.

Turbine Stop Valve Closure 4

4 1

1 11#

17.

Safety Injection Input y

from ESF 2

1 2

1, 2 9

s y

18.

Reactor Trip System Interlocks a.

Intermediate Range Neutron Flux, P-6 2

1 2

2,,

8 b.

Low Power Reactor i

Trips Block, P-7 P-10 Inptt 4

2 3

1 8

or' P-13 Input 2

1 2

1 0

c.

Power Range Neutron Flux, P-8 4

2 3

1 8

d.

Low Setpoint Power Range Neutron Flux, P-10 4

2 3

1, 2 8

e.

Turbine Impulse Chamber Pressure, P-3 2

1 2

1 8

4 a

TABLE 3.3-1 (Continued) j l

_ACTIONSTATEMENTS(Continue _dl l

ACTION 3 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a.

Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint, and b.

Above the P-6 (Intermediate Range Neutron Flax Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.

ACTION 5 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 With the number of OPERABLE channels one less than the Total Number of. Channels, STARTUP and/or POWER OPERATION may preceed provided the following conditions are satisfied:

a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and b.

The Minimuia Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.1.1 and Specification 4.3.2.1.

ACTION 7 - With the number of OPERABLE channels one less thar the Total Nu;nber of Channels, STARTUP and/or POWER OPERATIO.. may proceed until performance of the next required OPEk

'NAL TEST provided the inoperable channel is placed in,ne trippeo condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

~

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months datermine by observation of the associated permissive annunciator window (s) that the interleck is in its required state for the existing plant condition, or apply Specification 3.0.3.

Amendment No.10(Unit z)

McGUIRE - UNITS 1 and 2 3/4 3

Amendment No. 29 (Unit 1)

-e n

l TABLE 3:3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANL3Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor trip breakers within the next hour.

ACTION 11 - With the number of CPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

l

-McGUIRE - UNITS 1 and 2 3/4 3-8

TABLE 3.3-3 (Continued)

TABLE NOTATION

Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

1. Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam pressure is not blucked.

The provisions of Specification 3.0.4 are not applicable.

- These values left blank pending NRC approval of three loop operation.

ACTION STATEMENTS ACTION 14 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 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 ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 With the number of OPERABLE channels one less than the Total Nummer of Cnannels, operation may proceed until performance of the next required OPERATIONAL TEST provideri the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 16 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPEPABLE requirement is met.

One additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

ACTION 17 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge supply and exhaust valves are maintained closed.

1 l

McGUIRE - UNITS I and 2 3/4 3-23 i

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

ACTION 18 - With the number of 0FERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-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 SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 19 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

l a.

The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and l

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I

for surveillance testing of other channels per Specifica-l tion 4.3.L1 and Specification 4.3.2.1.

l ACTION 20 - With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, ba in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the l

other channel is OPERABLE.

)

ACTION 22 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to 0FERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANOBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the action required by Specification 3.7.1.4.

ACTION 24 - With the number of OPERABLE channels less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated auxiliary feedwater pump inoperable and take the action required by Specifica-tion 3.7.1.2.

With the channels associated with more than one auxiliary feedwater pemp inoperable, immediately declare the associated auxiliary feedwater pumps inoperable and take the action reqeired by Specification 3.7.1.2.

Amendment No.10 (Unit 2)

McGUIRE - UNITS I and 2 3/4 3-24 Amendment No.29 (Unit 1)

TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3.

Pressurizer Pressure-Low-Low a.

Safety Injection (ECCS) i 27(1)/12(3) b.

Reactor Trip (from SI) i2 c.

Feedwater Isolation

<9 d.

Containment Isolation-Phase "A"(2)

}18(3)/28(4) n.

Containment Purge and Exhaust Isolation N. A.

f.

Auxiliary Feedwater(5)

N.A.

g.

Nuclear Ser/ ice Water System 5 76(1)/65(3) h.

Component Cooling Water 1 76(1)/65(3) 1.

Start Diesel Generators 1 11 4.

Steam Line Pressure-Low 6.

Safety Injection (ECCS) 1 12(3)/22(4) b.

Reactor Trip (from SI) 12 c.

Feedwater Isolation 59 d.

Containment Isolation-Phase "A"(2)

$ 18(3)/28(4) e.

Containment Purge and Exhaust Isolation N.A.

f.

Auxiliary Feedwater(5)

N.A.

g.

Nuclear Service Water i 65(3)/76(4) h.

Steam Line Isolation

<7 1.

Coinponent Cooling Water 65(3)/7G(4) j.

Start Diesel Generators 1 11 5.

Containment Pressure--High-High a.

Containment Spray

_ 45 5.

Containment Isolation-Phase "B" N. A.

c.

Steam Line Isolation

_7 6.

Steam Generator Water Level--High-High a.

Turbine Trip N.A.

b.

Feedwater Isolation

_ 13 9

Amendment No.10 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 3-31 Amendment No. 29 (Unit 1)

TABl.E 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 7.

Steam Generator Water Level - Low-Low a.

Motor-driven. Auxiliary Feedwater Pumps 5 60 b.

Turbine-driven Auxiliary Feedwater Pumps 1 60 8.

Neoative Stesm Line Pressure Rate - high Steam Line Isolaticn 17 9.

Start Permissive Containment Pressure Control System N.A.

10.

Termination Containment Pressure Control System N.A.

11.

Auxiliary Feedwater Suction Pressure - Low Auxiliary Feedwater Pumps (Suction Supply Automatic Realigninent) 5 13

)

12.

RWST Level Automatic Switchover to Recirculation 1 60 13.

Station Blackout a.

Start Motor-Driven Auxiliary Feedwater Pumps 5 60 b.

Start Turbine-Driven Auxiliary Feedwater Pump 1 60 14.

Trip of Main Feedwater Pumps Start Motor-Driven Auxiliary Feedwater Pumps 5 60 15.

Loss of Power 4 kV Emergency Bus Undervoltage-1 11 Grid Degraded Voltage Amendment No.10 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 3-32 Amendment No.29 (Unit 1)

E TABLE 4.3-9 (Continued)

TABLE NOTATION AAt all times except when the isolaticn valve is closed and locked.

During WASTE GAS HOLDUP SYSTEM operation.

4 (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

a.

Instrument indicates measured levels above the Alarm / Trip Setpoint, b.

Circuit failure (alarm only), and c.

Instrument indicates a dour. scale failure (alarm only).

(2) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

Instrument indicates measured levels above the Alarm Setpoint, a.

b.

Circuit failure, and c.

Instrument indicates a downscale failure.

(3) The ' initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

These standards shall permit calibrating the system over its intended range of energy and measurement range.

For subsequent CHANN6L CALIBRATION, sources that have been related to the initial calibration shall be used.

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples corresponding to alarm setpoints in accordance with the manufacturer's recommendations.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples in accordance with the manufacturer's recommendations.

In addition, a standard gas sample of nominal 4 volume percent oxygen, balance nitrogen, shall be used in the calibration to check linearity of the oxygen a.v'yzer.

Amendment No.10 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 3-77 Amendment No. 29 (Unit 1) t

INSTRUMENTATION LOOSE-PART DETECTION SYSTEM I

LIMITING CONDITION FOR OPERATION 3.3.3.10 The Loose-Part Detection System shall be OPERABLE.

APPLICABILITY: MODES 1 and 2 ACTION:

a.

With one or mcre Loose-Part Detection System channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for rostoring the channel (s) to OPERABLE status.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each channel of the Loose-Part Detection Systems shall be demonstrated OPERABLE by performance of:

a.

A CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , and b.

An ANALOG CHANNEL OPERATIONAL TEST e cept for verification of Setpoint at least once per 31 days, and c.

A CHANNEL CALIBRATION at least one per 18 months.

McGUIRE - UNITS 1 and 2 3/4 3-78

2 TABLE 4.4-4 (Continued) r "g

TABLE NOTATION f r1

Until the specific activity of the Reactor Coolant System is restored within its limits.

c.

z a

y Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

w AAA gross radioactivity analysis shall consist of the quantitative measurement of the total specific activity

,g of the reactor coolant except for radionuclides with half-lives less than 10 minutes and all radioiodiries.

The total specific activity shall be the sum of the degassed beta gamma activity and the total of all m

identified gaseous activities in the sample within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the sample is taken and extrapolated back to when the sample was taken.

Determination of the contributors to the gross specific activity shall be based upon those energy peaks identifiable with a 95% confidence level. The latest available data may be used for pure beta-emitting radionuclides.

A radiochemical analysis for E shall cons.ist of the quantitative measurement of the specific activity for each radionuclide, exccpt for radionuclides with half-lives less than 10 minutes and all radiciodines; R

which is identified in the reactor coolant.

The specific activities for these individual radionuclides shall be used in the determination of E for the reactor coolant sample.

Determination of the contributors y

to E shall be based upon those energy peaks identifiaole with a 95% confidence level.

UI 1

i l

^

REACTOR COOLANT SYSTEM t

3/A.4.9 PRFSSURE/ TEMPERATURE LIMITS l

REACTOR COOLANT SYSTEM j

LIMITING CONDITION FOR OPERATION l

3.4.9.1 The Reactor Coolant Syste5 (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures j

3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and i

hydrostatic testing with:

a.

A maximum heatup of 100*F for Unit 1 and 60*F for Unit 2 in any 1-hour period, b.

A maximum cooldown of 100 F in any 1-hour period, and c.

A maximum teiperature change of less than er equal to 10*F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curvel.

s APPLICABILITY:

At all times.

ACTION:

With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; d2termine that the Reactor Coolant System remains acceptable for continued operation 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 the RCS T _ and pressure to less than 200*F and 500psig,respectively,withinthl'Yollowing30 hours.

SURVEILLANCE REQUIREMENTS f

4.4.9.1.1 The Reactor Coolant System temperature and' pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.

i 4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be remaved and examined, to determine changes in material properties, as required by 10 CFR 50, Appendix H in accordance with the schedule in Table 4.4-5.

The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.

t t

Amendment No.10 (Unit 2)

McGUIRE - UNITS ~1 and 2 3/4 4-30 Amendn9nt No.29 (Unit 1) l i

l

PLANT SYSTEMS TABLE 3.7-4b (Conti1ued)

SAFETY-RELATEDMECHANICALSNUBBERf PACIFIC SCIENTIFIC SMALL SIZE MEDIUM SIZE LARGE SIZE (350 lbs. or Less (1,487 Lbs. to (50,000 lbs. to SYSTEM ^*

TO 600 lbs) 15,000 lbs).

120,000 lbs)

SV 0

3 0

VE 1

3 0

VI 30 1

0 VQ 0

2 0

WG 2

0 0

WL 8

0 0

WS 2

0 0

YC 1

1 0

Subtotal (Unit 1) 375 282 23 UNIT 2 BB 67

$5 0

CA 9

59 0

CF 13 80 8

FW 0

4 1

KC 66 81 0

KD 3

1 0

KF 2

5 0

LD 0

2 0

NB 5

1 0

NC 100 95 2

ND 29 41 0

inubbers may be added or deleted without prior License Amendment to Table 3.7-4b provided that a revision to Table 3.7-4b is incl 0ded with the next License Amerdment request.

In lieu of any other report required by Specification 6.9.1, at least 15 days prior to the deletion of any listed snubber, a Special Report shall be prepared and submitted to the Commission in accordance with Specification 6.9.2 evaluating the safety significance of the proposed snubber removal.

- A listing of individual snubbers and m9re detailed information shall be available fnr NRC review at the McGuire Nuclear Station.

Amendment No.10(Unit 2)

McGUIRE - UNITS 1 and 2 3/4 7-27 Amendment No. 29(Unit 1)

o PLANT SYSTEMS TABLE 3.7-4b (Contin ~ued)

SAFETY-RELATED MECHANICAL SNUBBERS

PACIFIC SCIENTIFIC SMALL SIZE MEDIUM SIZE LARGE SIZE (350 lbs. or Less (1,487 Lbs. to (50,000 lbs. to SYSTEM **

TO 600 lbs) 15,000 lbs) 120,000 lbs)

NF 2

2 0

NI 56 55 3

NM 42 11 0

NR 10 8

0 NV 170 69 0

RF 1

3 0

RN 28 34 1

RV 9

8 0

SA 9

12 0

SM 2

24 30 Sv 0

1 0

TE 1

3 0

VE 3

2 0

VG 1

2 0

VI 26 1

0 VN O

4 0

VQ 3

1 0

v5 1

0 0

VX 2

1 0

WL 15 7

0 WN 0

2 0

Subtotal (Unit 2) 675 674 45 l

TOTAL for UNITS 1 and 2 1,003 956 655 l

" Snubbers may be added or deleted without prior License Amendment to Table 3.7-4b-i proviried that a revision to Table 3.7-4b is included with the next License Amendment request.

In lieu of any other reporf, required by Specification 6.9.1, at least 15 days prior to the deletion of any listed snubbar, a Special Report shall be prepared and submitted to the Commission in accordance with Specific-l ation 6.9.2 evaluating the safety significance of the proposed snubber removal.

- A listing of individual snubbers and ruore detailed information shall be available for NRC review at the McGuire Nuclear Station.

l Amendment No.10(Unit 2)

McGUIRE - UNITS 1 and 2 3/4 7-28 Amendment No. 29(Unit 1) l

PLANT SYSTEMS LIMITING CONDITION FOR OPERAT. ION (Continued)

APPLICABILITY:

Whenever equipment protected by the Spray / Sprinkler System is required to be OPERABLE.

ACTION:

a,

'ith one or more of the above required Spray and/or Sprinkler Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establich a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish a hourly fire watch patrol.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10.2 Each of the above required Spray and/or Sprinkler Systems shall be demonstrated OPERABLE:

a.

At least once per 31 days, by verifying that each valve (manual, power operated, or automatic) in the flow path which is accessible during plant operation is in its correct position, b.

At least once per 12 months, by cycling each testable valve in the flow path through at least one complete cycle of full travel, c.

At least once per 18 months:

1)

By performing a system functional test which includes simulated automatic actuation of the system, and:

a)

Verifying that the automatic valves in the flow path actuate to their correct position on a Fire Detection test signal, and b)

Cycling each valve in tne flow path that is not testable during plant operation through at least one complete cycle of full travel.

2)

By a visual inspection of the dry pipe spray and sprinkler headers to verify their integrity; and 3)

By a visual inspection of each nozzle's spray area to verify the spray pattern is not obstructed.

4)

By verifying that each valve (manual, power-operated, or automatic) in the flow path which is inaccessible during plant operatinn is in its correct position.

d.

At least once per 3 years, by performing an air flow test through each open head spray / sprinkler header and verifying each open head spray / sprinkler nozzle is unobstructed.

Amendment No.10 (Unit 2)

McGUI'!E - UNITS 1 and 2 3/4 7-35 Amendment No.29 (Unit 1)

PLANT SYS1 CMS HALON SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.10.3 The following Halon Systems shall be OPERABLE:

a.

Elevation 716.ft. - Auxiliary Building Room No.

Equipment 600 B Turbine Driven Aux. FW Pump - Unit 1 601B Turbine Driven Aux. FW Pump - Unit 2 b.

Elevation 733 ft. - Auxiliary Building Rocai No.

Equipment 703-704 Diesel Generators - Unit 1 714-719 Diesel Geerators - Unit 2 APPLICABILITY: Whenever equipment protected by the Italon System is required to be OPERABLE.

ACTION:

a.

With rne or more of the above required Halon Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire wat-h with backup fire suppression equipment for those area.s in which rodundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.10.3 Each of the above required Halon Systems shall be demonstrated OPERABLE:

a.

At leest once per 31 days, by verifyir.g that each valve (manual, power-operated, or automatic) in the flow path is in its correct

position, b.

At least once per 6 months, by verifying Halon storage tank weight to be at least 95% of full charge weight and pressure to be at least I

90% of full charge pressure, and c.

At least once per 18 months, by:

1)

Verifying the system, including associated ventilation dampers and fire door release mechanisms, actuatec manually and auto-matica11y, upon receipt of a simulated actuation signal, and 2)

Performance of a flow test through headers and nozzles to assure no blockage.

McGUIRE - UNITS 1 and 2 3/4 7-36 i

PLANT SYSTEMS I

FIRE HOSE STATIONS L!MITING CONOITION FOR OPERATION 3.7.10.4 The fire hose stations shown in Table 3.7-5 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hos7 stations is required to be OPERABLE.

ACTION:

a.

With one or more of the fire hose stations shown in Table 3.7-5 inoperable, provide gated wye (s) on the nearest OPERABLE hose station (s). _One outlet of the wye shall be connected to the standard length of hose provided for the hose station.

The second outlet of the wye shall be connected to a length of hose sufficient to provide coverage for the area left unprotected by the inoperable hose station. Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to operating technicians, plant equipment, or the hose itself,.the fire hose shall be stored in a roll at the outlet of the OPERABLE hose station.

Signs shall be mounted above the gated.ge(s) to identify the proper hose to use.

The above action shall be accomplished within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if tne inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicc51e.

SURVEILLANCE REQUIREMENTS 4.7.10.4 Each of the fire hose stations shown in Table 3.7-5 shall be demonstrated OPERABLE:

a.

At least once per 31 days,, by a visual inspection of the fire hose stations accessible during plant operations to assure all required equipment is at the station, b.

At least once per 18 months, by:

1)

Visual inspection of the stations not accessible during plant operations to assure all required equipment is at the station, 2)

Removing the hose for inspection and re-racking, and 3)

Inspecting all gaskets and replacing'any degraded gaskets in the couplings.

c.

At least once per 3 years, by:

l 1)

Partially opening each hose station valve to verify valve l

OPERABILITY and no flow blockage, and 2)

Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above maximum fire main operating pressure, whichever is greater, McGUIRE - UNITS I and 2 3/4 7-37 i

PLANT SYSTEMS Table 3.7-5 FIRE HOSE STATIONS NO.

LOCATION ELEVATION (FT) 157 55-FF 695 180 52-CC 716 181 54-GG 716 176 52-CC 716 175 52-CC 716 893 40-AA 733 891 40-CC 733 892 43/44-0D 733 895 46 BB 733 889 51/52-DD 733 888 52-EE 733 171 54-HH 733 167 51-JJ 733 168 52-MM 733 169 55-NN 733 962 46-CC 750 964 51-CC 750 965 54-BB 750 966 56-DD 750 971 58-BB 750 303 52-GG 750 162 54-LL 750 161 50-MM 750 164 56-QQ 750 974 51-BB 767 191 56-GG 767 184 54-KK 767 186 51-MM 767 158 57-FF 695 183 59-CC/DU 716 182 b8-GG 716 178 58/59-MM 716 179 61-LL 733 900 68-AA/BB 733 901 72-D0 733 902 68/69-D0 733 903 72-D0 733 914 66-BB 733 898 61-BB 733 899 66-BB 733 897 60-DD 733 896 60-EE 733 904 58-CC/DD 733 172 58-HH 733 174 61-JJ/KK 733 170 57-LL 733 Amendment No.10(Unit 2)

McGUIRE - UNITS 1 and 2 3/4 7-38 Amendment No.29(Unit 1)

l PLANT SYSTEMS j

SURVEILLANCE REQUIREMENTS (Continued) i 4.7.11.2 Each of the aoove required fire doors shall be verified OPERABLE by inspecting the automatic hold-open, release and closing mechanism and latches at least once per 6 months, and by verifying:

a.

That each unlocked fire door without electrical supervision is closed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

That doors with automatic hold-open and release mechanisms are free of obstructions at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and performing a functional test at least once per 18 months, c.

That each' locked closed fire door is closed at least once per 7 days, and d.

The OPERABILITY of the Fire Door Supervision System for each electrically supervised fire door by performing a TRIP ACTUATING DEVICE OPERATIONAL TEST at least once per 31 days.

l McGUIRE - UNITS 1 and 2 3/4 7-41 l

. ~.

e a

PLANT SYSTEMS 3/4.7.12 AREA TEMPERATURE MONITORING LIMITING CONDITION FOR OPERATION 1

J l

3.7.12 The temperature of each area shown in Table 3.7-6 shall be maintained within the limits indicated in Table 3.7-6.

APPLICABILITY:

Whenever the equipment in an affected area is required to be OPERABLE.

ACTION:

With one or more areas exceeding the temperature limit (s) shown in Table 3.7-6:

For more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , prepare and submit a Special Report to the a.

Commission pursuant to Specification 6.9.2 within the next 30 days providing a record of the amount by which and the cumulative time the terperature in the affected area exceeded its limit and an analysis to demonstrate the continued OPERABILITY of the affected equipment.

b.

By more than 30*F, in addition to the Special P.eport required above, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area to within its temperature limit or declare the equipment in the affected area inoperable.

SURVEILLANCE REQUIREMENTS 4.7.12 The temperature in each of the areas shown in Table 3.7-6 shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Amendment No10 (Unit 2)

McGUIRE - UNI 1 and 2 3/4 7-42 Amendment No29 (Unit 1)

4

[

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN LIMITING CONDITION FOR OPERAT ?N 3.10.1 The SHUT 00WN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control rod (s).

APPLICABILITY:

MODE 2.

ACTION:

a.

With any full-length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, imme-diately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Speci-fication 3.1.1.1 is restored.

b.

With all full-length control rods fully inserted and the reactor subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENlL 4.10.1.1 ihe position of each full-length control rod either partially or fully witndrawn shall b? determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full-length control rod not fully inserted shall bc demonstrated capable of full insertion when tripped frem at least the 50% withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reductag the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

1

\\

McGUIRE - UNITS 1 and 2 3/4 10-1

SPECIAL TEST EXCEPTIONS 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group 5eight, insertion, and power distribution limits of i

Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1, and 3.2.4 may be l

suspended during the performance of PHYSICS TESTS provided:

i a.

The THERMAL POWER is maintained less than or equal to 85% of RATED THERMAL POWER, and b.

The limits of Specifications 3.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specification 4.10.2.2 below.

APPLICABILITY: MODE 1.

ACTION:

I j

With any of_the limits of Specification 3.2.2 or 3.2.3 being exceeded while the requirements ot' Specifications 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1, and 3.2.4 are suspended, either:

Reduce THERMAL POWER sufficient to satisfy the ACTION requirements a.

of Specifications 3.2.2 and 3.2.3, or 4

b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to ba less than or equal to 85% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.2.2 The requirements of the below listed specifications shall be performed at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during PHYSICS TESTS:

a.

Specifications 4.2.2.2 and 4.2.2.3, and b.

. Specification 4.2.3.2.

5 McGUIRE - UNITS 1 and 2 3/4 10-2 Amendment No.10(Unit L) i Amends. ' No.29(Unit 1)

.

ML20087C014

Text

Attachment:

Attachment:

Navigation menu

Search