Text

Amend 84 to License NPF-63,revising TSs 3.0.4 & 4.0.4 IAW Guidance Provided in GL 87-09,by Removing Need to Explicitly Ref Applicability for Certain TSs
	ML18016A641
Person / Time
Site:	Harris
Issue date:	10/20/1998
From:	Hebdon F; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML18016A642	List: ML18016A641;
References
	NPF-63-A-084 NUDOCS 9810260264
	Download: ML18016A641 (72)
	v • d • e

'iRREou

~4

~o Cy ClO Cy

~O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 CAROLINAPOWER & L G CO PAN e al DO K

5 -400 HEA ON A RS U

E 0

E P

NTU T

D NT TO F I ITY PERATING LICENSE Amendment No. 84 License No. NPF-63 1.

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

A.

The application for amendment by Carolina Power 8 Light Company, (the licensee), dated August 27, 1998, as supplemented by letter dated October 1, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and 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; D.

The issuance of this amendment willnot 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 Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-63 is hereby amended to read as follows:

98i0260264 98f020 PDR ADOCK 05000400 P

PDR

0 I~E I

4~

(2) ec nica ecifica ion andE vi o e taIProecionPI n

The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No.

84, are hereby incorporated into this license.

Carolina Power 8 Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebdo, Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 20, 1998

0 J

I I

ACHMENTT LICE ME D

N NO 4

FA 0

E NGLCE S

PF-DO TN Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

emove 3/4 0-1 3/4 0-2 3/4 2-13 3/4 3-2 3/4 3-3 3/4 3-4 3/4 3-6 3/4 3-18 3/4 3-22 3/4 3-23 3/4 3-24 3/4 3-50 3/4 3-57 3/4 3-60 3/4 3-74 3/4 3-82 3/4 4-43 3/4 6-4 3/4 6-14 3/4 7-1 3/4.7-9 3/4 7-25 3/4 8-19 3/4 9-11 3/4 9-13 3/4 9-14 3/4 11-7 3/4 11-15 B 3/4 0-1 B 3/4 0-2

. B 3/40-2a B 3/4 0-2b B 3/4 0-3 es se P

s 3/4 0-1 3/4 0-2 3/4 2-13 3/4 3-2 3/4 3-3 3/4 3-4 3/4 3-6 3/4 3-18 3/4 3-22 3/4 3-23 3/4 3-24

, 3/4 3-50 3/4 3-57 3/4 3-60.

3/4 3-74 3/4 3-82 3/4 4-43 3/4 6-4 3/4 6-14 3/4 7-1 3/4 7-9 3/4 7-25 3/4 8-19 3/4 9-11 3/4 9-13 3/4 9-14 3/4 11-7 3/4 11-15 B 3/4 0-1 B 3/4 0-2 B 3/4 0-2a B 3/4 0-2b B 3/4 0-3

0 I

I

3 4.0 APPLICABILITY L INITING CONDITION FOR OPERATION 3.0:1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL NODES 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 unless otherwise noted in the ACTION statement.

3.0.3.

When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:

a.

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

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

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 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

'pecifications.

1 This specification is not applicable in NODE 5 or 6.

h 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified. time interval.

Entry into an OPERATIONAL NODE or specified condition may be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time.

This provision shall not prevent passage through or to OPERATIONAL NODES as required to comply with ACTION requirements or that are part of a shutdown of the unit.

Exceptions to these requirements are stated in the individual specifications.

3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.

This is an exception to 3.0.1 above for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

SHEARON HARRIS - UNIT 1

3/4 0-1 Amendment No. 84

ri I

~

I t

'PPLICABILITY SURVEILLANCE RE(UIREHENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL NODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

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

4.0.3 If it is discovered that a surveillance was not performed within its specified surveillance interval, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified surveillance interval, whichever is less.

This delay period is permitted to allow performance of the surveillance.

If the surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable ACTION requirements must be met.

When the surveillance is performed within the delay period and the surveillance criteria are not met, the LCO must immediately be declared not

met, and the applicable ACTION requirements must be met.

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

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

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

4.0.5 Surveillance Requirements for inservice inspection and testing of ASHE Code Class 1,

2, and 3 components shall be applicable as follows:

a ~

Inservice inspection of ASHE Code Class',

2, and 3 components and inservice testing-of ASHE Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASHE Boiler. and Pressure Vessel Code and applicable Addenda as required by 10 CFR Part 50, Section 50.55a(g),

except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i);

SHEARON HARRIS - UNIT 1

3/4 0-2 Amendment No. 84

0 J

~ ~

C E

POWER DISTRIBUTION ITS LIMITING CONDITION FOR OPERATION A~TI'N~

C~'

i d~

2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and 3.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least'once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater RATED THERMAL POWER.

SURVEILLANCE REQUIREMENTS 4,2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a.

Calculating the ratio at least once per 7 days when the alarm is

OPERABLE, and b.

Calculating the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady-state operation when the alarm is inoperable.

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one'Power Range channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetric thimble locations or full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SHEARON HARRIS - UNIT1'/4 2-13 Amendment No. 84

ll J

p

TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 1.

Manual Reactor Trip MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE OF CHANNELS TO TRIP OPERABLE MODES ACTION 2

1 2

l)2 1

2 1

2

. 3,4,5

-9 2.

3.

4.

7.

8.

9.

10.

Power Range, Neutron Flux a.

High Setpoint b.

Low Setpoint Power Range, Neutron Flux High Positive Rate Power Range, Neutron Flux, High Negative Rate Intermediate

Range, Neutron Flux Source

Range, Neutron Flux a.

Startup b.

Shutdown Overtemperature 5T Overpower hT Pressurizer Pressure--Low (Above P-7)

Pressurizer Pressure--High Pressurizer Water Level--High (Above P-7) 3 1,

2 1¹¹¹,

2 1,

2 I¹¹¹,

2 2¹¹ 3, 4, 5

1, 2

1 1,

2 1

2 2

6 6(1)

=6 SHEARON HARRIS - UNIT 1 3/4 3-2 Amendment No. 84

eh J

TABLE 3.3-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 12.

Reactor Coolant Flow--I ow a.

Single Loop (Above P-8) 13.

b.

Two Loops (Above P-7 and below P-8)

Steam Generator Water Level--Low-Low 15.

Undervoltage--Reactor Coolant Pumps (Above P-7) 14.

Steam Generator Water Level--Low Coincident With Steam/

Feedwater Flow Mismatch 3/1 oop 3/loop 3/stm.

gen.

2 stm.

gen.

level and 2 stm./feed-water flow mismatch in each stm.

gen.

2/loop in any operating loop 2/loop in two operating loops 2/stm.

gen.

in any operating stm.

gen.

1 stm.

gen.

level coincident with 1

stm./feedwater flow mismatch in same stm.

gen.,

2/pump 2/train TOTAL NO.

CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE 2/loop in each operating loop 2/loop in each operating loop 2/stm.

gen.

each operating stm.

gen.

1 stm.

gen. level and 2 stm./feed-water flow mismatch in same stm.

gen.

or 2

stm.

gen. level and 1-stm./feedwater flow mismatch in same stm.

gen.

2/tr ain 1,

2 6(1) 1, 2

APPLICABLE MODES ACTION ~

SHEARON HARRIS - UNIT 1

3/4 3-3 Amendment No. 84

J'l C

TABLE 3.3-1 Continued REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 16.

17.

18.

19.

Underfrequency--Reactor Cool ant Pumps (Above P-7)

Turbine Trip (Above P-7) a.

Low Fluid Oil Pressure b.

Turbine Throttle Valve Closure Safety Injection Input from ESF Reactor Trip System Interlocks a.

Intermediate Range Neutron Flux, 'P-6 b.

Low Power Reactor Trips Block, P-7

1) P-10 Input or

2) P-13 Input c.

Power Range Neutron Flux, P-8 d.

Power Range Neutron Flux, P-10 e.

Turbine Impulse Chamber

Pressure, P-13 1,

2 6

10 8

2¹¹ 1 j 2

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE OF CHANNELS TO TRIP OPERABLE MODES 'CTION 2/pump 2/train 2/train 1

6 SHEARON HARRIS - UNIT 1

Amendment No. 84

I'

~ '

TABLE 3.3-1 Continued TABLE NOTATIONS When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.

Whenever Reactor Trip Breakers are to be tested.

¹¹Below the P-6 (Intermediate Range Neutron Flux Inter lock) Setpoint.

¹¹¹Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(l)The applicable MODES and ACTION Statement for these channels noted in Table 3.3-3 are more restrictive and, therefore, applicable.

ACTION STATEMENTS ACTION 1 -

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

ACTION 2 -

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:

a.

The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , The Minimum Channels OPERABLE requirement is met;

however, the inoperable channel may be bypassed for up to.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3. 1. 1, and C.

Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

SHEARON HARRIS - UNIT 1'/4 3-6 Amendment No. 84

,I

TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 1.

Safety Injection (Reactor Trip, Feedwater Isolation, Control Room Isolation, Start Diesel Generators, Containment Ventilation Isolation, Phase A

Containment Isolation, Start Auxiliary Feedwater System Motor-Driven Pumps, Start Containment Fan Coolers, Start Emergency Service Water

Pumps, Start Emergency Service Water Booster Pumps) a.

Nanual Initiation

b. Automatic Actuation Logic and Actuation Relays MINIMUM TOTAL NO.

CHANNELS CHANNELS OF CHANNELS TO TRIP OPERABLE APPLICABLE NODES 1, 2, 3, 4

1, 2, 3, 4

ACTION 18 14 c.

Containment Pressure--High-1

d. Pressurizer Pressure--Low e.

Steam Line Pressure--Low 3/steam line 2

2 2

2/steam 2/steam line

. line in any steam line 1, 2, 3, 4

1, 2, 38 1, 2, 38 15 15 15 SHEARON HARRIS - UNIT 1 3/4 3-18 Amendment No. 84

0 J

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.

OF CHANNELS V

MINIMUM CHANNELS CHANNELS TO TRIP OPERABLE APPLICABLE MODES ACTION 4.

Hain Steam Line Isolation (Continued)

b. Automatic Actuation Logic and Actuation Relays c.

Containment Pressure--High-2 d.

Steam Line Pressure--Low e.

Negative Steam Line Pressure Rate--High 5.

Turbine Trip and Feedwater Isolation 1, 2, 3, 4

21 3

2 2

1 2

3 15 I

See Item l.e.

above for Steam Line Pressure--Low initiating functions and requirements.

3/steam 2 in any 2/steam.line 3

4 15 line.

steam line a.

Automatic Actuation Logic and-Actuation Relays b.

Steam Generator Mater Level--High-High (P-14) c: Safety Injection 4/stm.

gen.

2/stm.

geq.

3/stm.

gen.

1, 2

in any stm.

in each gen.

stm.

gen.

See Item l. above for all Safety Injection initiating functions and requirements.

19 SHEARON HARRIS - UNIT 1

3/4 3-22 Amendment No. B4

0 l

r

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT TOTAL NO.

CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS APPLICABLE OPERABLE MODES ACTION Auxiliary Feedwater a.

Manual Initiation 1)

Motor-Driven Pumps 2)

Turbine-Driven Pumps b.

Automatic Actuation Logic and Actuation Relays c.

Steam Generator Mater Level--Low-Low 1/pump 2/pump 2

1/pump 1/pump 1

1/pump 1, 2, 3

2/pump 1, 2, 3

2 1, 2, 3

23 23 21 1)

Start Hotor-Driven Pumps 3/stm.

gen.

2/stm.

gen.

in any stm.

gen.

2/stm.

gen.

in each stm.

gen.

1, 2, 3

15 I

2)

Start Turbine-Driven Pump d.

Safety Injection Start Motor-Driven Pumps e.

Loss-of-Offsite Power Start Motor-Driven Pumps and Turbine-Driven Pump f.

Trip of All Hain Feedwater Pumps Start Motor-Driven Pumps 1/pump 1/pump 1/pump 1,

2 3/stm.

gen.

2/stm.

gen.

2/stm.

1, 2, 3

in any 2

gen. in stm.

gen.

each stm.

gen.

See Item 1.

above for all Safety Injection initiating functions and requirements.

See Item 9. below for Loss of Offsite Power initiating functions and requirements.

i5

[

~

SHEARON HARRIS - UNIT 1

3/4 3-23 Amendment No. 84

I J

TABLE 3.3-3 Continued ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION FUNCTIONAL UNIT 6.

Auxiliary Feedwater (Continued) g.

Steam Line Differential Pressure--High Coincident With Main Steam Line Isolation (Causes AFW Isolation) 7.

Safety Injection Switchover to Containment Sump a.

Automatic Actuation Logic and Actuation Relays b.

RWST Level--Low-Low Coincident With Safety Injection 8.

Containment Spray Switch-over to Containment Sump a.

Automatic Actuation Logic and Actuation Relays TOTAL NO.

OF CHANNELS CHANNELS TO TRIP MINIMUM CHANNELS APPLICABLE OPERABLE MODES ACTION 3/steam line 2/steam line 2/steam 1,

2, 3

twice with any line steamline low See Item 4.

above for all Steam Line Isolation initiating functions.and requirements 2

1, 2, 3, 4

14 1,

2, 3, 4

14

.4 2

3 1,

2, 3, 4

16 See Item l. above for all Safety Injection initiating functions and requirements.

SHEARON HARRIS - UNIT 1 3/4 3-24 Amendment No. B4

INSTRUMENTATION 3 4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3. 1 The radiation monitoring instrumentation channels. for plant operations shown in Table 3.3-6 shall be OPERABLE with their Alarm/Trip Setpoints within the specified limits.

APPLICABILITY:

As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitoring channel Alarm/Trip Setpoint for plant operations exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specification 3.0.3 are not applicable.

SURYEILLANCE RE(UIREMENTS 4.3.3. 1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL

CHECK, CHANNEL CALIBRATION and DIGITAL CHANNEL OPERATIONAL TEST for the MODES and at the frequencies shown in Table 4,3-3.

SHEARON HARRIS - UNIT 1

3/4 3-50 Amendment No. B4

INSTRUMENTATION SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERABLE'PPLICABILITY:

At all times.

ACTION:

'a ~

With one or more of the above required seismic monitoring instruments 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 restoring the instrument(s) to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE(UIREMENTS 4.3.3.3.

1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and an ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4.

4.3.3.3.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01 g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a

CHANNEL CALIBRATION performed within 10 days following the seismic event.

Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion.

A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 14 days describing the magnitude, frequency spectrum, and resultant effect upon facility features impo} tant to

safety, SHEARON HARRIS - UNIT 1

3/4 3-57 Amendment No. 84

0 1

(p,'~

'NSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a.

b.

With one or more required meteorological monitoring channels inoperable for more than 7 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 restoring the channel(s) to OPERABLE status.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4,3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-5.

SHEARON HARRIS - UNIT I 3/4 3-60 Amendment No. 84

p eE

ry A

rw'a INSTRUMENTATION METAL IMPACT MONITORING SYSTEM LIMITING CONDITION FOR OPERATION 3.3.3.9 The Metal Impact Monitoring System shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

ACTION:

a

~

Mith one or more Metal Impact Monitoring 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 restoring the channel(s) to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4,3.3.9 Each channel of the Metal Impact Monitoring System 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 , b.

An ANALOG CHANNEL OPERATIONAL TEST, except for verific'ation of setpoint,.at least once per 31 days, and c.

A CHANNEL CALIBRATION at least once per 18 months.

SHEARON HARRIS - UNIT 1

3/4 3-74 Amendment No. B4

J'~

IJ

I ~

" INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION" LIMITING CONDITION FOR OPERATION.

3.3.3. 11 The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Specification 3. 11.2.5're not exceeded.

APPLICABILITY:

As shown in Table 3.3-13.

ACTION:

'a ~

With an explosive gas effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above specification declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b.

With the number of OPERABLE explosive gas monitoring instrumentation channels less than the Minimum Channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within 30 days, and if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why this inoperability was,not corrected in a

timely manner.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3. 11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-9.

'ote:

The radioactive gaseous effluent monitoring portions of Specification 3/4.3.3. 11 have been deleted from Technical Specifications and have been relocated to the ODCM.

SHEARON HARRIS - UNIT 1

3/4 3-82 Amendment No.

B4

n'

~

1

'REACTOR COOLANT SYS 3 4.4 '0 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4. 10 The structural integrity of ASHE Code Class 1,

2, and 3 components shall be maintained in accordance with Specification 4.4. 10.

APPLICABILITY: All MODES.

ACTION:

'a ~

b.

C.

With the structural integrity of any ASHE Code Class 1 compo'nent(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.

With the structural integrity of any ASHE Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to witliin its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.

With the structural integrity of any ASHE Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.

SURVEILLANCE RE(UIREHENTS 4.4. 10 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide

1. 14, Revision 1, August 1975.

SHEARON HARRIS - UNIT 1

3/4 4-43 Amendment No. 84

P'

'ONTAINMENT SYSTEM CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:

'a ~

Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.

An overall air lock leakage rate of less than or equal to 0.05 L, at P,.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

a

~

With one containment air lock door inoperable:

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed; 2.

3.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days; Otherwise, be in at least HOT STANDBY within the next 6

hours arid in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

I b.

With the containment air lock inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

'I Except during entry to repair an inoperable inner door, for a cumulative time not to'xceed one hour per year.

SHEARON HARRIS - UNIT 1

3/4 6-4 Amendment No.

B4

t

t~

'ONTAINMENT SYSTEMS 3 4.6. 3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 Each containment isolation valve specified in the Technical Specification Equipment List Program, plant procedure PLP-106, shall be OPERABLE with isolation times less than or equal to required isolation times.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the containment isolation valve(s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:

a ~

b.

c ~

d.

Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange, or Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE RE(UIREHENTS 4.6.3.

1 Each isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated

actuator, control or power circuit by performance of a cycling test, and verification of isolation time.

SHEARON HARRIS - UNIT 1

3/4 6-14 Amendment No. 84

I

I' 4.7 PLANT SYSTE 3 4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lift settings as specified in Table 3.7-2.

APPLICABILITY:

NODES 1, 2, and 3.

ACTION:

a 0 With one or more main steam line Code safety valves inoperable, operation may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE(UIREHENTS 4.7.1.1 No additional requirements other than those required by Specification 4.0.5.

SHEARON HARRIS - UNIT 1

3/4 7-1 Amendment No. 84

0 4I I

j

" PLANT SYSTEMS HAIN STEAN LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve (HSIV) shall be OPERABL'E.

APPLICABILITY:

MODES I, 2, 3, and 4.

ACTION:

MODE I:

With one HSIV inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 2, 3, and 4:

With one MSIV inoperable, subsequent operation in MODE 2, 3, or 4 may proceed provided the isolation valve is maintained closed.

Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

I SURVEILLANCE REQUIREMENTS 4.7.l.5 Each HSIV shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.

The provisions of Specification 4.0.4 are not applicable for entry into MODES 3 or 4.

SHEARON HARRIS - UNIT I 3/4 7-9 Amendment No. 84

r,'

I

" PLANT SYSTEMS 3 4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9 Each'ealed source (excluding startup sources and fission detectors previously subjected to core flux) containing radioactive material either in excess of 100 microCuries of beta and/or gamma emitting material or l0 microCuries of alpha emitting material shall be free of greater than or equal to 0.005 microCurie of removable contamination.

APPLICABILITY: At all times.

ACTION:

'a ~

With a sealed source having removable contamination in excess of the above limits, immediately withdraw the sealed source from use and either:

b.

I.

Decontaminate and repair the sealed

source, or 2.

Dispose of the sealed source in accordance with Commission Regulations.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.9. I Test Requirements

- Each sealed source shall be tested for leakage and/or contamination by:

a.

The licensee, or b.

Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microCurie per test sample.

4.7.9.2 Test Frequencies

- Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequency described below.

a 0

Sources in use

- At least once per 6 months for all sealed sources containing radioactive materials:

1.

With a half-life greater than 30 days (excluding Hydrogen 3),

and 2.

In any form other than gas.

SHEARON HARRIS - UNIT I 3/4 7-25 Amendment No. 84

0 t

'LECTRICAL POWER S

MS 3 4.8.4 ELECTRICAL E UIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.4. 1 Each containment penetration conductor overcurrent protective device specified in the Technical Specification Equipment List Program, plant procedure PLP-106, shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the containment penetration conductor overcur rent protective device(s) inoperable:

a.

Restore the protective device(s) to'PERABLE status or deenergize the circuit(s) by tripping the associated backup circuit breaker or racking out or removing the inoperable circuit breaker within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , declare the affected system or component inoperable,and verify the backup circuit breaker to be tripped or the inoperable circuit breaker racked out or removed at least once per 7 days thereafter,'or b.

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

SURVEILLANCE REQUIREMENTS 4.8.4.

1 Each containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:

a.

At least once per 18 months:

1.

By verifying that the 6900-volt circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers, and performing the following:

a)

A CHANNEL CALIBRATION of the associated protect'ive

relays, b)

An integrated syst'm functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed, and SHEARON HARRIS - UNIT 1

3/4 8-19 Amendment No. 84

S

REFUELING OPERATIONS 3 4. 9. 9 CONTAINMENT VENTILATION ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Ventilation Isolation System shall be OPERABLE.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

a.

b.

With the Containment Ventilation Isolation System inoperable, close each of the containment purge makeup and exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.

'he provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4,9.9 The Containment Ventilation Isolation System shall be demonstrated OPERABLE within IOO hours prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that containment ventilation isolation occurs on a two-out-of-four High Radiation test signal from the containment area radiation monitors (Table 3.3-6, item I.a) and by verifying that isolation occurs for each valve using its control switch in the main control room.

SHEARON HARRIS - UNIT I 3/4 9-ll Amendment No. B4

gt.

~

I

'\\

'EFUELING OPERATIO 3 4.9.11 WATER LEVEL -

NEW AND SPENT FUEL POOLS LIMITING CONDITION FOR OPERATION 3.9. 11 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated'n the storage racks:

APPLICABILITY:

Whenever irradiated fuel assemblies are in a pool.

ACTION:

a 0 With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the affected pool area and restore the water level to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.11 At least once per 7 days, when irradiated fuel assemblies are in a

pool, the water level in that pool shall be determined to be at least its minimum required depth.

SHEARON HARRIS - UNIT 1

3/4 9-13 Amendment No. B4

r~'

~

4

'EFUELING OPERATIO 3 4.9.12 FUEL HANDLING BUILDING EMERGENCY EXHAUST SYSTEM LIMITING CONDITION FOR OPERATION 3.9 '2 Two independent Fuel Handling Building Emergency Exhaust System Trains shall be OPERABLE.

APPLICABILITY:

Whenever irradiated fuel is in a storage pool.

ACTION:

a.

With "one Fuel Handling Building Emergency Exhaust System Train inoperable, fuel movement within the storage pool or crane operation with loads over the storage pool may proceed provided the OPERABLE Fuel Handling Building Emergency Exhaust System Train is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal adsorber.

b.

C.

With no Fuel Handling Building Emergency Exhaust System Trains

OPERABLE, suspend all operations involving movement of fuel within the storage pool or crane operation with loads over the storage pool until at least one Fuel Handling Building Emergency Exhaust System Train is restored to OPERABLE status.

The provisions of Specification 3.0.3 are. not applicable.,

SURVEILLANCE REQUIREMENTS 4.9. 12, The above required Fuel Handling Building Emergency Exhaust System trains shall be demonstrated OPERABLE:

a

~

b.

At least once per 31 days on a

STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber

housings, or (2) following significant painting, fire, or chemical release in any ventilation zone communicating with the system by:

Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.5.a, C.5.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the unit flow rate is 6600 cfm +

10% during system operation when tested in accordance with ANSI N510-1980.

SHEARON HARRIS - UNIT 1

3/4 9-14 Amendment No. 84

0

t/~

L RADIOACTIVE EFFLUE LI UID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases:

a.

Outside temporary tank, excluding demineralizer vessels and liners used to solidify or to dewater radioactive wastes.

APPLICABILITY: At all times.

ACTION:

b.

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank; within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Annual Radioactive Effluent Release

Report, pursuant to Specification 6.9. 1.4.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE(UIREHENTS

4. 11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a

representative sample of the tank's contents within 7 days following any addition of radioactive material to the tank.

Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to

. the Liquid Radwaste Treatment System.

SHEARON HARRIS - UNIT '1 3/4 11-7 Amendment No.

B4

I 4

I

RADIOACTIVE EFFLUEN EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION

3. 11.2.5 The concentration of oxygen in the GASEOUS RADWASTE TREATMENT SYSTEM downstream of the hydrogen recombiners shall be limited to less than or equal to 2/ by volume whenever the hydrogen concentration exceeds 4/ by volume.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in the GASEOUS RADWASTE TREATMENT SYSTEM downstream of the hydrogen recombiners greater than 2/ by volume but less than or equal to 4/ by volume, reduce the oxygen concentratio'n to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the GASEOUS RADWASTE TREATMENT SYSTEM downstream of the hydrogen recombiners greater than 4/ by

'olume and the hydrogen concentration greater than 4%%u by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4/ by

volume, then take ACTION a.,

above.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE(UIREMENTS

4. 11.2.5 The concentrations of hydrogen and oxygen in the GASEOUS RADWASTE TREATMENT SYSTEM shall be determined to be within the above limits by monitoring, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , the waste gases in the GASEOUS RADWASTE TREATMENT SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3. 11.

SHEARON HARRIS - UNIT 1

3/4 11-15 Amendment No.

B<

t I

3 4.0 APPLICABILI BASES The specifications of this section provide the general requirements applicable to each of the Limiting C'onditions for Operation and Surveillance Requirements within Section 3/4.

In the event of a disagreement between the requirements stated in these Technical Specifications and those stated in an applicable Federal Regulation or Act, the requirements stated in the applicable Federal Regulation or Act shall take precedence and shall be met.

3.0. 1 This specification defines the applicability of each specification in terms of defined OPERATIONAL MODES or other specified conditions and is provided to delineate'pecifically when each specification is applicable.

3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for Operation and associated ACTION requirement.

3.0.3 The specification delineates the measures to be taken for those circum-stances not directly provided for in the ACTION statements and whose occurrence would violate the intent of a specification.

For example, Specification 3.5.2 requires two independent ECCS subsystems to be OPERABLE and provides explicit ACTION requirements if one ECCS subsystem is inoperable.

Under the requirements of Specification 3.0.3, if both the required ECCS subsystems are inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measures must be initiated to place the unit 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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

As a further example, Specification 3.6.2.

1 requires two Containment Spray Systems to be OPERABLE and provides explicit ACTION requirements if one Spray System is inoperable.

Under the requirements of Specification 3.0.3, if. both the required Containment Spray Systems are inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measures must be initiated to place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and in COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

It is acceptable to initiate and complete a

reduction in OPERATIONAL MODES in a shorter time interval than required in the ACTION statement and to add the unused portion of this allowable out-of-service time to that provided for operation in subsequent lower OPERATION MODE(S).

Stated allowable out-of-service times are applicable regardless of the OPERATIONAL MODE(S) in which the inoperability is discovered but the times provided for achieving a mode reduction are not applicable if the inoperability is discovered in a mode lower than the applicable mode.

For example if the Containment Spray System was discovered to be inoperable while in STARTUP, the ACTION Statement would allow up to 156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months to achieve COLD SHUTDOWN. If HOT STANDBY is attained in 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months rather than the allowed 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months , 140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months would still be available before the plant would be required to be in COLD SHUTDOWN.

However, if this system was discovered to be

(

inoperable while in HOT STANDBY, the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided to achieve HOT STANDBY would.not be additive to the time available to achieve COLD SHUTDOWN so that the total allowable time is reduced from 156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months to 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months .

This specification is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternativ'es that would not result in redundant systems or components being inoperable.

3.0.4 This specification establishes limitations on MODE changes when a

Limiting Condition for Operation is not met.

It precludes placing the facility in a higher (LCO 3.0.4 is only applicable when entering MODE 4 from MODE 5, MODE 3 from MODE 4, MODE 2 from MODE 3, or MODE 1 from MODE 2)

MODE of SHEARON HARRIS - UNIT 1 B 3/4 0-1 Amendment No. 84

0 I

1

APPLICABILITY BASES 3.0,4 (Continued),

operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted.

The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits.

Compliance with ACTION requirements that permit continued operation of the facility for

- an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a

MODE change.

Therefore, in this case, entry into an OPERATIONAL MODE or other-specified condition may be made in accordance with the provisions of the ACTION requirements.

The provisions of this specification should not, however, 'be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

3.0.5 This specification establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS.

The sole purpose of this Specification is to provide an exception to 3.0. 1 (e.g., to not comply with the applicable Required Action(s)) to allow the performance of surveillance testing to demonstrate:

a.

The OPERABILITY of the equipment being returned to service; or b.

The OPERABILITY of other equipment The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the allowed surveillance tests.

This Specification does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being returned to service is reopening a containment isolation valve that has been closed to comply with Required Actions and must be reopened to perform the surveillance tests.

An example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to prevent the trip function from occurring during the performance of a surveillance test on another channel in the other trip system.

A similar example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of a surveillance test on another channel in the same trip system.

SHEARON HARRIS - UNIT 1

8 3/4 0-2 Amendment No. 84

0 0

h ra

APPLICABILITY BASES 1

4.0, I Thjs specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Conditions for Operation are applicable.

Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.

Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification.

4.0.2 The provisions of this specification establish the limit for which the specified time interval for Surveillance Requirements may be extended.

It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant'operating conditions that may not be suitable for conducting surveillance; e.g.,

transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibilityto accommodate the length'f a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.

Likewise, it is not the intent that the 18-month interval surveillances be performed during power operation unless it is consistent with safe plant operation.

The limitation of Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.

This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

4.0.3 Specification 4.0.3 establishes the flexibilityto defer declaring affected equipment inoperable or an affected variable outside the specified limits when a surveillance has not been completed within the specified surveillance interval.

A delay period of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified surveillance interval, whichever is less, applies from the point in time that it is discovered that the surveillance has not been performed in accordance with Specification 4.0.2, and not at the time that the specified surveillance interval was not met.

This delay period provides adequate time to complete surveillances that have been missed.

This delay period permits the completion of a surveillance before complying with ACTION requirements or other remedial measures that might preclude completion of the surveillance.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the surveillance, the safety significance of the delay in completing the required surveillance, and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the requirements.

When a surveillance with a surveillance interval based not on time intervals, but upon specified unit conditions or operational situations, is discovered not to have been performed when specified, Specification 4.0.3 allows the full delay period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform the surveillance.

SHEARON HARRIS - UNIT I B 3/4 0-2a Amendment No. 84

0 P

I V

APPLICABILITY BASES 4.0.,3 (Continued)

Specification 4.0.3 also provides a time limit for completion of surveillances that become applicable as a consequence of MODE changes imposed by ACTION requirements.

Failure to comply with specified surveillance intervals for surveillance requirements is expected to be an infrequent occurrence.

Use of the delay period established by Specification 4.0.3 is a flexibilitywhich is not intended to be used as an operational convenience to extend surveillance intervals, If'a surveillance is not completed within the allowed delay period, then the equipment is considered inoperable or the variable is considered outside the specified limits and the time limits of the ACTION requirements for the applicable LCO begin immediately upon expiration of the delay period.

If a surveillance is failed within the delay period, then the equipment is inoperable or the variable is outside the specified limits, and the time limits of the ACTION requirements for the applicable LCO begin immediately upon the failure of the surveillance.

'I 8

Completion of the surveillance within the delay period allowed by this Specification, or within the completion time of the ACTIONS, restores compliance with Specification 4.0. I.

4.0.4 This specification establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement.

The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

SHEARON HARRIS - UNIT I 8 3/4 0-2b Amendment No. B4

/

r~

r4

APPLICABILITY BASES 4.0.5 This specification, ensures that 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 will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.

Relief from any of the above requirements has been provided in writing by. the Commission and is not a part of these Technical Specifications.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.

For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps to be tested up to 1 week after return to normal operation.

And for example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

SHEARON HARRIS - UNIT 1

8 3/4 0-3 Amendment No.

B4

'(

0 I

,e'

ML18016A641

Text

Attachment:

Navigation menu

Search