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Amend 100 to License NPF-22,revises Stated Requirement in Sections 3.0.4,4.0.4,3.3.7.5 Action 80,4.3.7.5,3.4.2 Action C & 4.4.2 of TSs
	ML17158A118
Person / Time
Site:	Susquehanna
Issue date:	01/31/1994
From:	Calvo J; Office of Nuclear Reactor Regulation
To:	;
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ML17158A119	List: ML17158A118; ML17158A120;
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENNSYLVANIA POWER

& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.

DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNI 2

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100 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 5 Light Company, dated January 24,

1994, 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.

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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) Tec n cal S ecifications and Environmental Protection P an The Technical Specifications contained in Appendix A, as revised through Amendment No. 1OO and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.

PPEL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and will remain in effect until the next unit shutdown of sufficient duration to allow for containment entry, not to exceed the sixth refueling and inspection outage.

FOR THE NUCLEAR REGULATORY COMMISSION

'ose A. Calvo, Assistant Director for Region I Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

january 31, 1994

ATTACHMENT TO LICENSE AMENDMENT NO.

FACILITY 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 contain vertical lines indicating the area of change.

The overleaf pages are provided to maintain document completeness.*

REMOV 3/4 0-1 3/4 0-2 3/4 3-71 3/4 3-72

~

3/4 3-73 3/4 3-74 3/4 4-5 3/4 4-6 INSERT 3/4 0-1 3/4 0-2 3/4 3-71 3/4 3-72*

3/4 3-73 3/4 3-74*

3/4 4-5 3/4 4-6*

3 4.0 APPLICABILITY LIMITINGCONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

If the Limiting Condition for, Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall be initiated to place the unit in an OPERATIONALCONDITION in which the Specification does not apply by placing it, as applicable, in:

1. At least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

3. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Where corrective measures are completed that permit operation under the ACTION

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requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual Specifications.

This specification is not applicable in OPERATIONAL CONDITION 4 or 5, 3.0.4 Entry into an OPERATIONAL CONDITION or other specified condition shall not be made when the conditions forthe Limiting Conditions for Operation are not met and the associated ACTION re uires a shutdown if the are not met within a s ecified time interval. Ent into an OPERATIONALCONDITIONor other s ecified condition ma be made in accordance with the ACTION re uirements when conformance to them ermits continued o eration of the facili for an unlimited eriod of time.

This provision shall not prevent passage through or to OPERATIONALCONDITIONS as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual Specifications.

Compliance with this Specification for the inoperable "S" SRV acoustic monitor is not required for the period beginning January 21, 1994, until the next unit shutdown of sufficient duration to allow for containment entry, not to exceed the sixth refueling end inspection outage.

SUSQUEHANNA - UNIT 2 3/4 0-1 Amendment No. If3, <<'0

APPLICABILITY SURVEILLANCE REQUIREIVIENTS 4.0.1 4.0.2 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

II, Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined b S ecification 4.0.2 shall constitute noncompliance with the OPERABILITYrequirements for a Limiting Condition for Operation.

The time limits of the ACTION re uirements are a

licable at the time it is identified that a

Surveillance Re uirement has not been e

rmed. The ACTION re uirements ma bedela edforu to24hoursto ermitthecom Ietionofthesurveillance whenthe allowable outa e time limits of the ACTION re uirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirement(s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.

This rovision shall not revent assa e throu h or to OPERATIONAL CONDITIONS as re uired to com I

with ACTION re uirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, 5 3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2,and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler nd Pressure Vessel Code and applicable Addenda as required by. 10 CFR 50,,Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

I

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

Not applicable to 18 month survelllances required to be performed prior to the startup following the end of the Unit 2 Third Refueling and Inspection Outage.

Compliance with this Specification for the inoperable "S" SRV acoustic monitor is not required for the period beginning January 21, 1994, until the next unit shutdown of sufficient duration to allow for containment entry, not to exceed the sixth refueling and inspection outage.

SUSQUEHANNA - UNIT 2 3/4 0-2 Amendment No. HS.

coC co0Cmx Rz C

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'"REQUSKP. NVIitSKRl""

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:OF,,'CHANlRS".!:i 1.

Reactor Vessel Steam Dome Pressure

2. Reactor Vessel Water Level

3. Suppression Chamber Water Level

4. Suppression Chamber Water Temperature

5. Suppression Chamber AirTemperature 8, 6 locations 6, 1/location TABLE3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION 80 80 80 80 80 1,2 1,2 1,2 1,2 1,2 CD CD

6. Primary Containment Pressure

7. Drywall Temperature

8. Drywall Gaseous Analyzer a.

Oxygen b.

Hydrogen

9. Safety/Relief Valve Position Indicators

10. Containment High Radiation

11. Noble gas monitors'.

Reactor Bldg. Vent b.

SGTS Vent c.

Turbine Bldg. Vent

12. Primary Containment Isolation Valve Position

13. Neutron Flux 2/range 2

2 1/valve,¹¹ 1

1 1

1/valve 1/range 1/valve,¹¹ 1

1 1

1/valve 80 80 80 82 80 81 81 81 81 80 80

1. 2 1,2 1,¹ 2¹ 1,¹ 2¹

1. 2 1,2 1,2 and 2 and

~~',2 1,2

1. 2

¹¹ Compliance with.these requirements'for'the'-': S"-:SRVacoustic monitor is'not"required for the per'iod beginning January 21, 1994, until the next unit shutdown of sufficient duration to allow for containment e'ntry,'not'to 'exceed the sixth refueling and inspection outage.

ACTION 80 "

TABLE 3.3.7.5-1 (Continued)

ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel(s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel(s) 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 SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 81 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirement, initiate the preplanned alternate method of monitoring the appropriate parameter(s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable channel(s) to OPERABLE status within 7 days of the event, or 2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

l ACTION 82-a.

With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirements of Table 3.3.7.5-1, restore at least one channel to OPERABLE statu's within 7 days or be in at least HOT SHUTDOWN within the next 12.hours.

SUS(UEHANNA - UNIT 2 3/4 3-72 Amendment No.

AUG 3 0 l988

,".':.:ACCIDENT:;lMONlTORlMG:,:IMSTRUMENTATIOM,SURVEILLANCE REQUIREMENTS'.(-

.~;.; ",:-:: '.i'.,"g",.:,,'":.'.,",,",;,::,,", INSTNJMEhlT.!~'4?';;,:."i:.';~l',(:,";!'.".":,';"',:;.':.!,"-;i:':-;CHANMB;CHECK".l~li!.,CHANMB CAUBRATION~'~

1.

Reactor Vessel Steam Oome Pressure 2.

Reactor Vessel Water Level 3.

Suppression Chamber Water Level 4.

Suppression Chamber Water Temperature 5.

Suppression Chamber AirTemperature 6.

Primary Containment Pressure 7.

Drywell Temperature 8.

Orywell Oxygen/Hydrogen Analyzer R

Q 9.

Safety/Relief Valve Position Indicators 10.

Containment High Radiation R¹ R

11.

Noble Gas Monitors

a. Reactor Bldg. Vent

b. SGTS Vent

c. Turbine Bldg. Vent 12.

Primary Containment Isolation Valve Position 13.

Neutron Flux M

M M

R R

R NA For hydrogen analyzer, use sample gas containing;

a. Nominal zero volume percent hydrogen, balance nitrogen.

b. Nominal thirty volume percent'hydrogen, balance nitrogen.

CHANNEL CALIBRATIONshall consist of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr and a one point calibration check of the detector below 10 R/hr with an installed or portable gamma source.

Compliance with these requirements for the "S" SRV acoustic monitor is not required for the period beginning January 21, 1994, until the next unit shutdown of sufficient duration to allow for containment entry, not to exceed the sixth refueling and inspection outage.

SUSQUEHANNA - UNIT 2 3/4 3-73 Amendment No. 100

INSTRUMENTATION SOURCE RANGE MONITORS LIMITING CONDITION FOR OPERATION 3.3.7.6 At least three source range monitor channels shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 2", 3, and 4.

ACTION:

a.

In OPERATIONAL CONDITION 2" with one of the above required source range monitor channels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

In OPERATIONAL CONDITION 3 or 4 with two or more of the above required source range monitor channels inoperable, verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

c.

The provisions of Specification 3.0.4 are not applicable for entry into Operational Condition 2 or 3 from Operational Condition l.

SURVEILLANCE RE UIREMENTS

4. 3. 7. 6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:

a ~

b.

C.

d.

Performance of a:

1.

CHANNEL CHECK at least once per:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months in CONDITION 2", and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in CONDITION 3 or 4, 2.

CHANNEL CALIBRATION""at least once per 18 months.

Performance. of a CHANNEL FUNCTIONAL TEST:

1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to moving the reactor mode switch from the Shutdown position, if not performed within the previous 7 days, and 2.

At least once per 31 days.

Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.7 cps""" with the detector fully inserted.

The provisions of Specification 4.0.4 are not applicable for entry into Operational Condition 2 or 3 from Operational Condition 1.

"With IRM's on range 2 or below.

"Neutron detectors may be excluded from CHANNEL CALIBRATION.

"""Provided signal-to-noise ratio is

> 2.

Otherwise, 3 cps.

SUS(UEHANNA - UNIT 2 3/4 3-74 AMENDMENT NO.

7-"'RS:

Ni

REACTOR COOLANT SYSTEM 3 4.4.2 SAFETY RELIEF VALVES LIMITINGCONDITION FOR OPERATION 3.4.2 The safety valve function of at least 10 of the following reactor coolant system safety/relief valves shall be OPERABLE with the specified code safety valve function liftsettings:

2 safety-relief valves 5 1146 psig k1%

4 safety-relief valves I 1175 psig ~1%

4 safety-relief valves 5 1185 psig s1%

3 safety-relief valves 5 1195 psig ~1'/o 3 safety-relief valves I 1205 psig a1%

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, AND 3.

ACTION:

a.

b.

c With the safety valve function of one or more of the above required safety/relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With one or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 105'F, close the stuck open relief valve(s); if unable to close the open valve(s) within 2 minutes or if suppression pool water temperature is 105'F or greater, place the reactor mode switch in the Shutdown position.

With one or more safety/relief valve acoustic monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCEREQUIREMENTS 4.4.2>>>>>> The acoustic monitor for each safety/relief valve shall be demonstrated OPERABLE with the setpoint verified to be 0.25 of the full open noise level>> by performance of a:

a.

CHANNEL FUNCTIONALTEST at least once per 31 days, and a b.

Calibration in accordance with procedures prepared in conjunction with its manufacturer's recommendations at least once per 18 months.>>"

The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

Up to 2 inoperable valves may be replaced with spare OPERABLE valves with lower setpoints until the next refueling.

Initial setting shall be in accordance with the manufacturer's recommendation.

Adjustment to the valve full open noise level shall be accomplished, during the startup test program.

The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam pressure is adequate to perform the test.

Compliance with these requirements for the "S" SRV acoustic monitor is not required for the period beginning January 21, 1994, until the next unit shutdown of sufficient duration to allow for containment entry, not to exceed the sixth refueling and inspection outage.

SUSQUEHANNA - UNIT 2 3/4 4-5

'Amendment No. 100

REACTOR COOLANT SYSTEM 3/4.4,3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3. 1 At least the following reactor coolant system leakage detection systems shall be OPERABLE:

a.

Two drywell floor drain sump level channels, and b.

One primary containment atmosphere gaseous radioactivity monitoring system channel and one containment atmosphere particulate radioactivity monitoring system channel aligned to the drywell.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a ~

b.

With one or both channels of the drywell floor drain sump level monitoring system inoperable, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ."

With both channels of the gaseous radioactivity monitoring system inoperable or with both channels of the particulate radioactivity monitoring system inoperable, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

If at least one channel of the affected monitoring systea cannot be returned to OPERABLE status and aligned to the drywell within 30 days, or the grab samples are not obtained and analyzed as required, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE RE UIREMENTS 4,4.3. 1 The reactor coolant system leakage detection systems shall be demonstrated OPERABLE by:

a.

Primary containment atmosphere particulate and gaseous monitoring systems-performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , a

CHANNEL FUNCTIONAL TEST at least once per 31 days and a

CHANNEL CALIBRATION at least once per 18 months.

b.

Drywell floor drain sump level monitoring system-performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days and a

CHANNEL CALIBRATION at least once per 18 months.

SUSQUEHANNA - UNIT 2 3/4 4-6 Amendment No ~

53 ev 4.~S

ML17158A118

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