ML17158A858

Amends 152 & 122 to Licenses NPF-14 & NPF-22,respectively, Modifying Applicable Operational Conditions for Secondary Containment Isolation Radiation Monitors Located on Refueling Floor & Radiation Monitor

ML17158A858
Person / Time
Site:	Susquehanna
Issue date:	08/24/1995
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Pennsylvania Power & Light Co, Allegheny Electric Cooperative
Shared Package
ML17158A859	List: ML17158A858 ML17158A860
References
NPF-14-A-152, NPF-22-A-122 NUDOCS 9508300357
Download: ML17158A858 (15)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 PENNSYLVANIA POWER 3 LIGHT COMPANY ALLEGHENY ELECTRIC COO RA V

INC

~OQMET NO. 50-38 SUS UEHANNA STEAM ELECTRIC STATION UNIT 1

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. i52 License No.

NPF-14 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for the amendment filed by the Pennsylvania Power 5 Light Company, dated February 1,

1995, as supplemented by letter dated June 20,

1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, 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 amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

9508300357 950824

(

PDR ADQCK 05000387 PDR L!

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:

(2)

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P otectio lan The Technical Specifications contained in Appendix A, as revised through Amendment No.

152 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

PP&L 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 and is to be implemented within 30 days after its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION n F. Stolz, Dire r

oject Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 24, i gg5

TTACHMENT TO GENS AMENDM NT NO. "

FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specification with enclosed pages.

The revised pages are identified by Amendment number and contains vertical lines indicating the area of change.

REMOVE 3/4 3-11 3/4 3-16 3/4 3-23 3/4 3-26 NSERT 3/4 3-11 3/4 3-16 3/4 3-23 3/4 3-26

TABLE 3.3.2-1 ISOLATION ACTUATIONINSTRUMENTATION TRIP FUNCTION ISOLATION SIGNAL(s)

MINIMUMOPERABLE CHANNELS PER TRIP SYSTEM APPLICABLE OPERATIONAL CONDITION ACTION a.

Reactor Vessel Water Level 1)

Low, Level 3 2)

Low Low, Level 2 3)

Low Low Low, Level 1

b.

Drywell Pressure

- High c.

Manual Initiation d.

SGTS Exhaust Radiation - High e.

Main Steam Line Radiation - High A

B X

Y,Z,X NA R

C 1.2 3 1.2,3 1.2.3 1.2,3 1.2.3 3 4%%% 5%%%

1.2.3 20 20 20 20 24 20 20 a.

Reactor Vessel Water Level - Low Low, Level 2 b.

Drywell Pressure

- High c.

Refuel Floor High Exhaust Duct Radiation - High d.

Railroad Access Shaft Exhaust Duct Radiation - High e.

Refuel Floor Wall Exhaust Duct Radiation - High f.

Manual Initiation 1,2,3 and "

1.2.3

¹

¹¹ 1,2,3 and "

25 25 25 25 25 24

TABLE3.3.2-1 (Continued)

ISOLATION ACTUATIONINSTRUMENTATION ACTION STATEMENTS ACTION 20 ACTION 21 ACTION 22 ACTION 23 ACTION 24 ACTION 25 ACTION 26 Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the next hour and declare the affected system inoperable or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Establish SECONDARY CONTAINMENTINTEGRITYwith the standby gas treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Lock the affected system isolation valves closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.

When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

Actuates dampers shown in Table 3.6.5.2-1.

When VENTING or PURGING the drywell per Specification 3.11.2.8.

When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with the potential for draining the reactor vessel.

Single control rod movement, except for the purpose of SDM demonstration (TS 3.10.3), is excluded.

¹¹ When handling irradiated fuel within the Railroad Access Shaft, and above the Railroad Access Shaft with the Railroad Access Shaft Equipment Hatch open.

(a)

See Specification 3.6.3, Table 3.6.3-1 for valves which are actuated by these isolation signals.

(b)

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the channel or trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

In addition, for the HPCI system and RCIC system isolation, provided that the redundant isolation valve, inboard or outboard, as applicable, in each line is OPERABLE and all required actuation instrumentation for that valve is OPERABLE, one channel may be placed in an inoperable status for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for required surveillance without placing the channel or trip system in the tripped condition.

SUSQUEHANNA - UNIT 1 3/4 3-16 Amendment No.

gg, 15/

(h 0)0Cmx zz Cz TRIP FUNCTION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION TABLE4.3.2.1-1 ISOLATION ACTUATIONINSTRUMENTATIONSURVEILLANCEREQUIREMENTS OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED Ca)

Ca)

(al a.

Reactor Vessel Water Level-1)

Low, Level 3 2)

Low Low, Level 2 3)

Low Low Low, Level 1

b.

Drywell Pressure

- High c.

Manual Initiation d.

SGTS Exhaust Radiation - High e.

Main Steam Line Radiation - High S

S S

NA NA S

S M

M M

M R

M M

R R

R R

NA R

R 1.2 3 1.2.3 1.2.3 1.2 3 1.2 3 2 3 4%%%

1 2.3 3

CL 0

a.

Reactor Vessel Water Level - Low Low, Level 2 b.

Drywell Pressure

- High c.

Refuel Floor High Exhaust Duct Radiation - High d.

Railroad Access Shaft Exhaust Duct Radiation - High e.

Refuel Floor Wall Exhaust Duct Radiation - High f.

Manual Initiation NA S

NA Q

R 1,2,3 and "

123 1,2,3 and "

V)C U)0Cm z

Cz TRIP FUNCTION CHANNEL CHECK CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST J5QL5IIQ5, (continued)

TABLE4.3.2.1-1 (Continued)

ISOLATION ACTUATIONINSTRUMENTATIONSURVEILLANCEREQUIREMENTS OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED d.

HPCI Equipment Room Temperature - High e.

HPCI Equipment Room b, Temperature

- High f.

HPCI Emergency Area Cooler Temperature - High g.

HPCI Pipe Routing Area Temperature - High h.

HPCI Pipe Routing Area b, Temperature - High i.

Manual Initiation j.

Drywell Pressure

- High NA NA NA NA NA NA NA M

M M

M M

R M

Q Q

Q Q

Q NA R

1.2.3 1.2.3 1,2,3 1.2.3 1,2,3 1,2,3 1.2.3 a.

Reactor Vessel Water Level - Low, Level 3 b.

Reactor Vessel (RHR Cut-in Permissive) Pressure-High c.

RHR Flow - High d.

Manual Initiation e.

Drywell Pressure

- High S

NA S

NA NA M

R M

R 0

R NA R

1,2.3 1,2,3 1.2.3 1,2,3 1.2.3 3

CL z0 When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

When any turbine stop valve is open.

When VENTING or PURGING the drywell per Specification 3.11.2.8.

¹ When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with the potential for draining the reactor vessel.

Single control rod movement, except for the purpose of SDM demonstration (TS 3.10.3), is excluded.

¹¹ When handling irradiated fuel within the Railroad Access Shaft, and above the Railroad Access Shaft with the Railroad Access Shaft Equipment Hatch open.

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 SYLVANIA POWER G

COMPANY GHENY ELECTRIC COOP A

VE INC.

DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No 122 License No. NPF-22 1.

The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A.

The application for the amendment filed by the Pennsylvania Power Light Company, dated February 1,

1995, as supplemented by letter dated June 20,

1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, 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 amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifica tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

122 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license.

PP&L 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 and is to be implemented within 30 days after its date of issuance FOR THE NUCLEAR RE LATORY COHHISSION J

n

. Stolz, Direc P

o ect Directorate I-2 D'sion of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 24,

]995

ATTACHMENT TO LICENSE AMENDMENT NO.

122 FAC ITY OPERATING LICENSE NO.

NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contains vertical lines indicating the area of change.

REMOV 3/4 3-11 3/4 3-16 3/4 3-23 3/4 3-26 INSERT 3/4 3-11 3/4 3-16 3/4 3-23 3/4 3-26

e (hC (D0 mz zz z

Q.

z0 TABLE 3.3.2-1 ISOLATION ACTUATIONINSTRUMENTATION TRIP FUNCTION ISOLATION SIGNAL(s)

MINIMUMOPERABLE CHANNELS PER TRIP SYSTEM a.

Reactor Vessel Water Level 1)

Low, Level 3 2)

Low Low, Level 2 3)

Low Low Low, Level 1

b.

Drywell Pressure

- High c.

Manual Initiation d.

SGTS Exhaust Radiation - High e.

Main Steam Line Radiation - High A

8 X

Y,Z NA R

C

~

a.

Reactor Vessel Water Level - Low Low, Level 2 b.

Drywell Pressure

- High c.

Refuel Floor High Exhaust Duct Radiation - High d.

Railroad Access Shaft. Exhaust Duct Radiation - High e.

Refuel Floor Wall Exhaust Duct Radiation - High f.

Manual Initiation NA APPLICABLE OPERATIONAL CONDITION 1.2 3 1.2 3 1.2.3 1.2.3 1.2.3 1 2 3 4'"'"""

1.2.3 1,2,3 and "

1.2 3

¹ 1,2,3 and "

ACTION 20 20 20 20 24 20 20 25 25 25 25 25 24

TABLE 3.3.2-1 (Continued)

~

ISOLATIONACTUATIONINSTRUMENTATION ACTION STATEMENTS ACTION 20 ACTION 21 ACTION 22 ACTION 23 ACTION 24 ACTION 25 ACTION 26 Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the next hour and declare the affected system inoperable or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Establish SECONDARY CONTAINMENTINTEGRITYwith the standby gas treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Lock the affected system isolation valves closed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.

When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

Actuates dampers shown in Table 3.6.5.2-1.

When VENTING or PURGING the drywell per Specification 3.11.2.8.

When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with the potential for draining the reactor vessel.

Single control rod movement, except for the purpose of SDM demonstration (TS 3.10.3), is excluded.

¹¹ When handling irradiated fuel within the Railroad Access Shaft, and above the Railroad Access Shaft with the Railroad Access Shaft Equipment Hatch open.

(a)

See Specification 3.6.3, Table 3.6.3-1 for valves which are actuated by these isolation signals.

(b)

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the channel or trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

In addition, for the HPCI system and RCIC system isolation, provided that the redundant isolation valve, inboard or outboard, as applicable, in each line is OPERABLE and all required actuation instrumentation for that valve is OPERABLE, one channel may be placed in an inoperable status for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for required surveillance without placing the channel or trip system in the tripped condition.

SUSQUEHANNA - UNIT 2 3/4 3-16 Amendment No. 122

U)C (h0Cmx zz Cz TRIP FUNCTION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION TABLE4.3.2.1-1 ISOLATION ACTUATIONINSTRUMENTATIONSURVEILLANCEREQUIREMENTS OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED Ca)

GD hJ Col a.

Reactor Vessel Water Level-1)

Low, Level 3 2)

Low Low, Level 2 3)

Low Low Low, Level 1

b.

Drywell Pressure

- High c.

Manual Initiation d.

SGTS Exhaust Radiation - High e.

Main Steam Line Radiation - High S

S S

NA NA S

S M

M M

M R

M M

R R

R R

NA R

R 1.2.3 1,2,3 1.2.3 1.2.3 1.2.3 1.2.3

'z O

fO PO a.

Reactor Vessel Water Level - Low Low,-

Level 2 b.

Drywell Pressure - High c.

Refuel Floor High Exhaust Duct Radiation - High d.

Railroad Access Shaft Exhaust Duct Radiation - High e.

Refuel Floor Wall Exhaust Duct Radiation - High f.

Manual Initiation NA S

NA Q

R 1,2,3 and

+

1,2,3¹ 1,2,3 and "

MC U)0 x

z I

Cz TRIP FUNCTION CHANNEL CHECK CHANNEL CHANNEL FUNCTIONAL CALIBRATION TEST IGQlhIIQ5. (continued)

TABLE4.3.2.1-1 (Continued)

-ISOLATIONACTUATIONINSTRUMENTATIONSURVEILLANCEREQUIREMENTS OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE REQUIRED 4)

Ca) t4 0) d.

HPCI Equipment Room Temperature - High e.

HPCI Equipment Room d, Temperature

- High f.

HPCI Emergency Area Cooler Temperature

- High g.

HPCI Pipe Routing Area Temperature

- High h.

HPCI Pipe Routing Area d, Temperature

- High i.

Manual Initiation j.

Drywell Pressure

- High NA NA NA.

NA NA NA NA M

M M

M M

R M

Q Q

Q Q

Q NA R

1.2.3 1.2.3 1,2,3 1.2.3 1.2.3 1.2.3

'1.2,3 a.

Reactor Vessel Water Level - Low, Level 3 b.

Reactor Vessel (RHR Cut-in Permissive) Pressure-High c.

RHR Flow - High d.

Manual Initiation e.

Drywell Pressure

- High S

NA S

NA NA M

M M

R M

R Q

R NA R

1.2 3 1.2 3 1.2.3 1.2.3 1.2,3 3

R O

ECL fO PO

¹¹ When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

When any turbine stop valve is open.

When VENTING or PURGING the drywell per Specification 3.11.2.8.

When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with the potential for draining the reactor vessel.

Single control rod movement, except for the purpose of SDM demonstration (TS 3.10.3), is excluded.

When handling irradiated fuel within the Railroad Access Shaft, and above the Railroad Access Shaft with the Railroad Access Shaft Equipment Hatch open.

I ht J