Text

Amends 51 & 32 to Licenses NPF-9 & NPF-17,respectively, Revising Tech Specs to Increase Allowed Containment Overall Integrated Leakage Rate by 50% & Provide for Retention of QA Activity Records
	ML20154L927
Person / Time
Site:	McGuire, Mcguire
Issue date:	03/05/1986
From:	Youngblood B; Office of Nuclear Reactor Regulation
To:	;
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UNITED STATES p

l NUCLEAR REGULATORY COMMISSION p

.. y WASHING TON. D. C. 20555 5

DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 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 Operating License No. NPF-9 filed by the Duke Power Company (licensee) dated April 25, 1985, September 6, 1985 and August 20, 1985, as supplemen.',ed November 6,1985, and January 28, 1986, 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 confctmity with the application, as amended, the provisions of the Act, and the regulations of the Comission; I

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 license amendment will not be inimical to the common 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-9 is hereby amended to read as follows:

1

(?) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.51, 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 Original signed by:

D. Hood

.[

B. J. Youngblood, Director

/

PWR Project Directorate #4 Division of PWR Licensing-A

Attachment:

Technical Specification Changes Date of Issuance: March 5, 1986

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UNITED STATES 8

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DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.32 License No. NPF-17 1.

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

A.

The applications for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility O Power Company (licensee) perating License No. NPF-17 filed by the Duke dated April 25, 1985, September 6,1985 and August 20, 1985, as supplemented November 6,1985, and January 28, 1986, 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 conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; 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 Commission'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 tne public; 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.

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. NTF-17 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.32, are hereby incorporated into the license.

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2-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 REGULATORY COMMISSION N

Original signed byr D. Hood

'b,\\. B. J. Youngblood, Director r

PWR Project Directorate #4 Division of PWR Licensing-A

Attachment:

Appendix A Technical Specification Changes Date of Issuance: March 5, 1986 yJll dJ/# [^

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i ATTACHMENT TO LICENSE AMENDMENT NO. 51 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT NO. 32 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 Page 3/4 3-20 3/4 3-19 3/4 3-249 (new page) 3/4 3-27 3/4 3-36 3/* 3-35 3/4 3-37 3/4 3-38 3/4 6-2 6-23 0

v V

'v' pc E

TABLE 3.3-3 (Continued) j{

ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION EE 23 MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE

[l FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

{

4.

Steam Line Isolation n>

a.

Manual Initiation 1)

System 2

1 2

1,2,3 22 2)

Individual 1/ steam line 1/ steam line 1/ operating 1,2.3 23 steam line b.

Automatic Actuation 2

1 2

1,2,3 21 Logic and Actuation Relays u,

c.

Containment Pressure--

4 2

3 1,2,3 16 3:

High-High i'

d.

Negative Steam Line Gs Pressure Rate - High Four Loops 3/ steam line 2/ steam line 2/ steam line 3

15*

Operating in any steam line Three Loops

(**)

Operating e.

Steam Line Pressure - Low Four Loops 3/ steam line 2/ steam line 2/ steam line 1,2,3 15*

Operating in any steam line Three Loops

(**)

Operating

TABLE 3.3-3 (Continued) r x

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION E5 R

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION c:

25 Ut 5.

Turbine Trip &

Feedwater Isolation i

g k

a.

Automatic Actuation 2

1 2

1, 2 5e 21 Logic and Actuation m

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 stm. gen.

c.

Doghouse Water 3/ train /

2/ train /

1, 2 25*

R!

Level (Feedwater Doghouse Doghouse Doghouse Isolation Only)

Y E!

6.

Containment Pressure Control

Syste, a.

Start Permissive 4/ train 2/ train 3/ train 1, 2, 3, 4 19*

b.

Termination 4/ train 2/ train 3/ train 1, 2, 3, 4 19*

El aa 29 M,.8 1

LL M

EE 33 BC

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 continuously until both trains are restored to operable status.

i MCGUIRE - UNITS 1 & 2 3/4 3-24a Amendment No. 51 (Unit 1) l Amendment No. 32 (Unit 2)

I TABLE 3.3-4 (Continued) i ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 5

5 FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 4.

Steam Line Isolation

~

l d

a.

Manual Initiation N.A.

N.A.

w

-l ni b.

Automatic Actuation Logic N.A.

N.A.

I E

and Actuation Relays m

1 j

c.

Containment Pressure--High-High 5 2.9 psig 5 3.0 psig i

d.

legative Steam Line 5 -100 psi /sec 5 -120 psi /sec

.ressure Rate - High e.

Steam Line Pressure - Low

> 585 psig

> 565 psig y

5.

Turbine Trip and Feedwater Isolation J

T a.

Automatic Actuation Logic N.A.

N.A.

O and Actuation Relays b.

Steam Generator Water level--

< 82% of narrow range

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

Instrument span each steam Tnstrument span each steam generator generator El c.

Doghouse Water Level-High 12" 13"

((

(Feedwater Isolation Only)

BB

%{

6.

Containment Pressure Control System i

yy a.

Start Permissive 5 0.25 psid 5 0.25 psid w vih b.

Termination 5 0.25 psid 5 0.25 psid 11 c+,+

8 i

TABLE 4.3-2 (Continued) 2 E)

{h ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS m

e TRIP c:

E3 ANALOG ACTUATING MODES UI CHANNEL DEVICE MASTER SLAVE FOR WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE w FUNCTIONAL UNIT CHEC.<

$3

,_ CAllBRATION TEST TEST LO':'" TEST TEST

' TEST IS REQUIRED

'I.ContainmentIsolation a.

Phase "A" Isolation

~

1) Manual Initiation N.A.

N.A.

N. A.

R N.A.

N.A.

1, 2, 3, 4

2) Automatic Actua-N.A.

N.A.

M(1)

Q 1, 2, 3, 4 tinn Logic and Actuation Relays

3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

$h b.

Phase "B" Isolation g>

1) Manual Initiation N.A.

N.A.

R N.A.

N.A.

1, 2, 3, 4 u5

2) Automatic Actua-N.A.

N.A.

M(1)

Q 1,2,34 tion Logic and Actuation Relays

3) Containment S

R H

N.A.

1,2,3 Pressure-High-High c.

Purge and Exhaust Isolation

1) Manual Initiation N.A.

N.A.

N. A.

R N.A.

N.A.

1,2,3,4

2) Automatic Actua-N.A.

N.A.

N.A M(1)

M(1)

Q 1,2,3,4 tiog logic and Actuation Relays

3) Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

TABLE 4.3-2 (Continued)

!F ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION g

SURVEILLANCE REQUIREMENTS i

5 TRIP i

ANALOG ACTUATING MODES 4

i c

CHANNEL DEVICE MASTER SLAVE FOR WHICH' 3

CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUAlION RELAY RELAY SURVEILLANCE!

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

[

4. Steam Line Isolation ro a.

Manual Initiation M.A.

N.A.

R N.A.

N.A.

1, 2, 3 b.

Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2, 3 Logic and Actuation Relays c.

Containment Pressure-- S R

M N.A.

N.A.

1,2,3 i

Hi h-High C

um d.

Necative Steam Line S

R M

N.A.

3 1

Pressure Rate-High

[

e.

Strim Line S

R M

N.A.

1, 2, 3 m

Pressure--Low

5. Turbine Trip and Feedwater Isolation a.

Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2 Logic and Actuation

((

Relay hh b.

Steam Generator Water S R

M N.A.

N.A.

1, 2 l

gg Level-High-High (P-14)

((

c.

Doghouse Water S

N.A.

R N.A.

N.A.

1, 2 o.o Level-High (Feddwater Isolation Only) w,[

6. Containment Pressure Control System a.

Start Permissive S

R M

N.A.

1, 2, 3, 4

((

b.

Termination S

R M

N. 7,.

N.A.

1, 2, 3, 4 vv I

e TABLE 4.3-2 (Continued) z ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

TRIP s

ANALOG ACTUATING MODES c

CHANNEL DEVICE MASTER SLAVE FOR WHICH l

5 CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE d

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

[

7. AuxO iary Feedwater i

E a.

Manual Initiation N.A.

N.A.

R N.A.

N.A.

1,2,3

~

b.

Automatic Actuation N.A.

N.A.

M(1)

Q 1, 2, 3 Logic and Actuation 1

Relays c.

Steam Generator Water S R

M N.A.

N.A.

N.A N.A.

1,2,3 Level--Low-Low w

d.

Auxiliary Feedwater N.A.

R N.A.

N.A.

1, 2, 3 1

Suction Pressure-Low

{

e.

Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements f.

Station Blackout N.A.

N.A.

N.A R

N.A.

1,2,3 l

g.

Trip of Main Feedwater N.A.

N.A.

R N.A.

N.A.

N.A 1, 2 Pum.'s

8. Automatic Switchover to Recirculation

)

gg

((

RSWT Level S

R M

N.A.

1, 2, 3 ll

9. Loss of Power 4 kV Emergency Bus N.A.

R N.A.

M N.A.

N.A.

N.A 1, 2, 3, 4 EE Und4 voltage-Grid j

hb Dec aded Voltage 1

22

' S.

< + < +

w

1 TABLE 4.3-2 (Continued) 1 E

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION hh SURVEILLANCE REQUIREMENfS TRIP ANALOG -

ACTUATING MODES E

CHANNEL DEVICE MASTER SLAVE FOR WHICH El CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

[,FUNCTIONALUNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED 10.

Engineered Safety s

Features Actuation

[

System Interlocks a.

Pressurizer N. A.

R H

N.A.

1, 2, 3 Pressure, P-11 b.

Reactor Trip, P-4 N. A.

N.A.

N.A.

R N.A.

N.A.

1, 2, 3 Low, Low T,,g, P-12 N.A.

R M

N.A.

1,2,3 c.

5 d.

Steam Generator 3

Level, P-14 5

R M

N.A.

M(1)

Q 1,2,3 oo t

+

. W

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% by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P,,,14.8 psig, or 2)

Less than or equal to L, 0.14% by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a r$duced pressure of P ' 7*4 PSI '

t 9

b.

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

and A combined bypass leakage rate of less than 0.07 L, for all c.

penetrations identified in Table 3.6-1 as secondary containment bypass leakage paths when pressurized to P,.

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 ratef8rallpenekr,ationsandvalvessubjecttoTypesBandCtestsexceeding 0.60 L, or (c) the combined bypass leakage rate exceeding 0.07 L restor $theoverallintegratedleakageratetolessthan0.75L or equal to 0.75 L, as applicable, and the combined leakage rafe$r, less for all oenetrations -and vklves subject to Type B and C tests to less than 0.60 L,,

and the combined bypass leakage rate to less than 0.07 L prior to increasing the Reactor Coolant System temperature above f00'F.

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-fled in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972 or the mass plot method:

Amendment No.32 (Unit 2)

McGUIRE - UNITS 1 and 2 3/4 6-2 Amendment No. 51 (Unit 1)

n ADMINISTRATIVE CONTROLS 1

1 RECORD RETENTION (Continued) g.

. Records of training and qualification for current members of the unit staff; h.

Records of iraervice inspections performed pursuant to these Technical Specifications; i.

Records of reviews performed for changes made to procedures or l

equipment or reviews of tests and experiments pursuant to 10 CFR 50.59; j.

Records of meetings of.the NSRB and reports required by l

Specification 6.5.1.12; k.

Records of the service lives of all snubbers Ifsted in Tables 3.7-4a l

and 3.7-4b including the date at which the service life commences and associated installation and maintenance records; 1.

Records of secondary water sampling and water quality; and Records of analyses required by the Radiological Environmental l

m.

Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date.

This should include procedures effective at specified times and QA records showing that these procedures were followed.

6.10.3 Records of quality assurance activities required by the QA Manual shall be retained for a period of time required by ANSI N45.2.9-1974.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20 each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall te controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

neaitn Physics personnel or personnel escorted by Health Physics personnel S

shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radia-tion areas.

McGUIRE - UNITS 1 and 2 6-23 Amendment No.51(Unit 1)

Amendment No.32(Unit 2) o

ML20154L927

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