Text

Amend 19 to License NPF-57,revising Applicability of Limiting Conditions for Operation & Surveillance Requirements Per Tech Specs 3.04,4.03 & 4.04
	ML20155F290
Person / Time
Site:	Hope Creek
Issue date:	09/28/1988
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20155F294	List: ML20155F290; ML20155F301;
References
	NUDOCS 8810130213
	Download: ML20155F290 (60)
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$2 KE0 Vg e.

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g UNITED STATES g

NUCLEAR REGULATORY COMMISSION g-l WASHING TON, D. C. 20555

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PUBLIC SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.19 License No. NPF-57 1.

The Nuclear Regulatory Comission (the Commission or the N/.C) has found that:

A.

The application for amendment filed by the Public Service Electric &'

Gas Company (PSE&G) dated April 28, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954. as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisinns of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance: (i) that the activities Nthorized by this amendment can be conducted without endangering the health and safety of the oublic, 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 Facility Operating License No. NPF-57 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A. as revised through Amendment No.19. and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

PSE&G shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, 8010130213 8G0928 gDR ADOCK0500g4

s o,

-2 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/S/

Walter R. Butler Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 28, 1988 I

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

FOR THE NUCLEAR REGULATORY COMMISSION

,[

4-Walter R. Butler. Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Peactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 28, 1988

ATTACHMENT TO LICENSE AMEN 0 MENT NO.19 FACILITY OPERATING LICENSE NO. NPF-57 DOCKET NO. 50-354 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages provided to maintain document completeness.*

Remove Insert 3/4 0-1 3/4 0-1 3/4 0-2 3/4 0-2 3/4 0-3 3/4 0-3 3/4 1-15*

3/4 1-15*

3/4 1-16 3/4 1-16 I

3/4 3-35 3/4 3-35 3/4 3-36*

3/4 3-36*

3/4 3-57*

3/4 3-58 3/4 3-58 3/4 3-67*

3/4 3-67*

3/4 3-68 3/4 3-68 3/4 3-71 3/4 3-71 3/4 3-72*

3/4 3-72*

3/4 3-85*

3/4 3-86 3/4 3-86 3/4 3-89 3/4 3-89 3/4 3-89a 3/4 3-89a*

l 3/4 3-90 3/4 3-90 3/4 3-01 3/4 3-91 3/4 3-92*

3/4 3-92*

3/4 3-95*

3/4 3-96 3/4 3-96 I

3/4 3-103 3/4 3-103 3/4 3-104 3/4 3-104*

I I

4 2-Remove Insert N

3/4 4-27 3/4 4-27 3/4 4-28*

3/4 4-28*

3/4 4-29 3/4 4-29 r-3/4 7-19 3/4 7-19 3/4 7-20*

3/4 7-20*

3/4 9-17*

3/4 9-18 3/4 9-18 4

3/4 11-5 3/4 11-5 3/4 11-6 3/4 11-6 j

3/4 11-7 3/4 11-7 l

'4 3/4 11-8 3/4 11-8

i 3/4 11-11*

3/4 11-11*

3/4 11-12 3/4 11-12 i

3/4 11-13 3/4 11-13 3/4 11 14 3/4 11-14 S

3/4 11-15 3/4 11-1.5 3/4 11-16 3/4 11-16 3/4 11-17*

3/4 11-17*

1 3/4 11-18 3/4 11-18 3/4 11-19 3/4 11-19 3/4 11-20 3/4 11-20 3/4 12-1*

3/4 12-1*

3/4 12-2 3/4 12-2 3/4 12-13 3/4 12-13 3/4 12-14 3/4 12-14 8 3/4 0-1 B 3/4 0-1 B 3/4 0-2 B 3/4 0-2 B 3/4 0-3 8 3/4 0-3 B 3/4 0-4 B 3/4 0-5 B 3/4 0-6

3/4.0 APPLICABILITY LIMITING CONDITION 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 initi-ated to place the unit in an OPERATIONAL CONDITION 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 SHUT 00WN 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 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.

Exceptiens to these requirements are stated in the individual Specifications.

This Specification is not applicable in OPERATIONAL CONDITIONS 4 or 5.

3.0.4 Entry into an OP6 RATIONAL CONDITION or other specified condition shall not be made when the conditions for the Limiting Condition 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 CONDITION or other specified condition may be made in accordance with the 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 CONDITIONS as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual Specifications.

HOPE CREEK 3/4 0-1 Amendment No.

19

APPLICABILITY SURVEILLANCF. REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless othemise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a.

A maximun allowable extension not to exceed 25% of the surveillance interval, but b.

The combined time interval for any 3 consecutive surveillance inter-vals shall not exceed 3.25 times the specified surveillance interval.

~

4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements 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 condi-tion 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 othe mise specified.

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

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applica'ule as follows:

Inservice inspection of ASME Code Class 1, 2, and 3 components and a.

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 and 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) i (6) (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 HOPE CREEK 3/4 0-2 Amendment No.

19

^

l a

APPLICABILITY S_URVEILLANCE REQUIREMENTS (Continued)

Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Required frequencies Code and aptlicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days c.

The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities.

d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

e.

Nothing in the ASME Boiler and Pressure Vessel Code chall be con-strued to supersede the requirements of any Technical Specification.

~

1 l

l HOPE CREEK 3/4 0-3 Amendment No.19 i

f l

REACTIVITY CONTROL SYSTEMS CONTROL ROD ORIVE HOUSING SUPPORT LIMITING CONDITION FOR OPERATION 3.1.3.8 The control rod drive housing support shall be in place.

APPLICABILITY: OPERATIONAL CON 0!TIONS 1, 2 and 3.

ACTION:

With the control rod drive housing support not in place, 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 following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.8 The control rod drive housing support shall be verified to be in place by a visual inspection prior to startup any time it has been disassembleu or when maintenance has been performed in the control rod drive housing support area.

1 H0PE CREEK 3/4 1-15

RE/.CTIVITY CONTROL SYSTEMS 3/4.1.4 CONTROL ROD PROGRAM CONTROLS R00 WORTH MINIMIZER LIMITING CONDITION FOR OPERATION 3.1. 4.1 The rod worth minimizer (RWM) shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2*#, when THERMAL POWER is less than or equal to 20% of RATED THERMAL POWEA, the minimum allowable low power setpoint.

ACTION:

i With the RWM inoperable, verify control rod movement and compliance a.

with the prescribed control rod pattern by a second licensed operator or other technically qualified member of the unit technical staff who is present at the reactor control console. Otherwise control rod movement may be only by actuating the manual scram or, placing the reactor mode switch in the Shutdown position.

SURVEILLANCE REQUIREMENTS 4.1.4.1 The RWM shall be demonstrated OPERABLE:

In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to withdrawal of a.

control rods for the purpose of making the reactor critical, and in OPERATIONAL CONDITION 1 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to RWH automatic initia-tion when reducing THERMAL POWER, by verifying proper indication of the selection error of at least one out-of-sequence control rod.

b.

In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to withdrawal of control rods for the purpose of making the reactor critical, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod.

In OPERATIONAL CONDITION 1 within one hour after RWM automatic c.

initiation when reducing THERMAL POWER, by verifying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod.

d.

By verifying that the control rod patterns and saqJence input to the RWM computer are correctly loaded following any loading of the program into the computer.

"Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the OPERABILITY of the RWM prior to withdrawal of control tods for the purpose of bringing the reactor to criticality.

See Special Test Exception 3.10.2.

HOPE CREEK 3/4 1-16 Amendment No. 19

.. - -. - -. - - _. _ - ~ -

o.

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels pt+ Trip Function requirement:

With one char.nel ir w able, place the ir.5perable channel a.

in the tripped cond. ion within one hour or declare the l

O associated systee moperable, b.

With more than one channel inoperable, declare the associated syste'a inoperable.

ACTION 31 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, declare the associated ECCs inoperable.

ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

ACTION 33 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or ueclare the associated ECCS inoperable.

ACTION 34 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

a.

For one channel inoperable, place the inoperable channel in the tripped condition within I hour or declare the HPCI l system inoperable.

b.

With more than one channel inoperable, declare the HDCI system inoperable.

ACTION 35 -

With the number of OPERABLE channels less than required by the Minimum CPERABLE Channels per Trip function requirement, place at least one inoperable channel in the tripped condition within one hour or declare the HPCI system ineparable.

ACTION 36 -

With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within I hour; operation may than continue until l

performance of the next required CHANNEL FUNCTIONAL TEST.

ACITON 37 -

With the number of 0PERA8LE r.hannels less than required by the Minimum OPERABLE channels per Trip Function requirement, open the minimum flow bypass valve within one hour.

Restore the inoperable channel to OPERA 8LE status within 7 days or declare the associated ECCS inoperable.

l HOPE CREEK 3/4 3 35 Amendment No.19

T.iBLE 3.3.3-2 52 D.ERGENCY CORE C00l.ING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS n

R Alloun8tE Q

TRIP FUNCTION TRIP SETPO!NT VALUE 4

1.

CORE SPRAY SYSTEM l

a.

Reactor Vessel hter Level - Low Low Low, Level 1' 1-129 f r:ches*

1-136 inches j

b.

Drywell Pressure - High

< 1.68 psig i 1.88 psig c.

Reactor Vessel Pressure - Low 461 psig i 481 ptly and I

1441 Psig l

d.

Core Spray Pump Discharge Flow - Low (8ypass)

> 775 gpa 1 650 gym l

e.

Core Spray Pump Start Time Delay - Normal Power 10 seconds 1 9 seconds and

< 11 seconds f.

Core Spray Pimp Start Time Delay - Emergency Power 6 seconds

[5secondsand

< 7 seconds o

g.

Manual Initiation MA NA A

2.

LOW PRESSURE C00LAKT IMECTION MODE OF MNt SYSTEM w

l l

a.

Reactor Vessel Water Level - Low Low Low, Level 1 1-129 inches

1-136 inches b.

Drywell Pressure - High

< 1.68 psig i 1.88 psig c.

Reactor Vessel Pressure - Low (Permissive) 450 psig i 460 psig and 1 440 psig l

d.

LPCI Pump Discharge Flow - Low (Bypass)

> 1250 gpa 1 1100 gpa e.

LPCI Pump Start Time Delay - Nonnal Power 5 seconds 1 4 second.s and

< 6 seconds f.

Manual Initiation MA NA l

3.

HIGH PRESSURE COOLANT I MECTION SYSTEM i

j a.

Reactor Vessel Water Level - (Low Low, Level 2) 1-38 inches

3-45 inches l

b.

Drywell Pressure - High

$ 1.68 psig i 1.88 psig c.

Condensate Storage Tank Level - Low 1 22,558 gallons 3 19,174 gallons d.

Suppression Pool Water tevel - High

< 78.5 inches

< 80.3 inches l

e.

Reactor Vessel Water Level - High, Levei 8 1 54 inches

[61 inches f.

HPCI Pump Discharge Flow - Low (Bypass) 1 550 gpa 1 500 gpa g.

Manual Inftiation MA NA I

i b

TA8LE 3.3.6-1 CONTROL 200 SLOCK INSTRistENTATION g

A MINIfRDI APPLICA8tE OPERABLE CHANNELS OPERATIONAL n

R TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION N

ROD BLOCK 8eNITOR ')

I 1.

a.

Upscale 2

la 60 b.

Inoperative 2

la 60 c.

Downscale 2

la 60 2.

APAN a.

Flow Biased Neutron Flux -

Upscale 4

1 61 b.

Inoperative 4

1, 2, 5 61 c.

Downscale 4

1 61

( f4eutron Flux - Upscale, Startup 4

2, 5 61 3.

%34d RANGE MONITORS

'i. "? $ector not full inIDI 3

2 E'

2 5

61 Upscale (C) b.

5 Inoperative (c) 3 2

61 c.

2 5

61 I

d.

Downscale 4

INTERNEDIATE RANGE peNITORS a.

Detector not full in 6

2, 5 61 b.

Upscale 6

2, 5 61 Inoperatig) 6 2, 5 61 c.

d.

Downscale 6

2, 5 61 5.

SCRAM DISCHA8GE VOLUME a.

Water Level-Nigh (Float Switch) 2 1, 2, 5**

62 6.

REACTOR COOLANT SYSTEN RECIRCULATION FLOW a.

Upscale 2

1 62 b.

Inoperative 2

1 62 c.

Comparator 2

1 62 7.

REACTOR N00E SWITCH SHUTDOWN POSITION 2

3, 4 63

TABLE 3.3.6-1 (Continued)

CONTROL R00 BLOCK INSTRUMENTATION ACTION ACTION 60 Declare the RBM inoperable and take the ACTION required by Specification 3.1.4.3.

ACTION 61 With the number of OPERABLE Channels:

a.

One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restere the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.

b Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped conditi'>n within one hour.

With the number of OPERABLE channels less than required by the ACTION 62 Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.

I With the number of OPERABLE channels less than required by the ACTION 63

' Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.

NOTES With THERMAL POWER > 30% of RATED THERMAL POWER.

With more than one control rod withdrawn.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

a.

The RBM shall be automatically bypassed when a peripheral control rod is

selected, b.

This function shall be automatically bypassed if detector count rate is

> 100 cps or the IRM channels are on range 3 or higher, c.

This function shall be 7utomatically bypassed when the associated IRM channels are on range 8 or highar, d.

This function shall be automatically bypassed when the IRM channels are on range 3 or higher.

e.

This function shall be automatically bypassed when the IRM channels are on range 1.

HOPE CREEK 3/4 3-58 Amendment No. 19

2 I

i TABLE 4.3.7.1-1 (Continued) 6 RADIATION MONITORING INSTRWENTATION SURVEILLANCE REQUIREMENTS l

m l

g m

j TA8tE NOTATION m

With fuel in the new fuel storage vault.

Nith fuel in the spent fuel storage pool.

When irradiated fuel is being handled in the secondary containment.

- When the offgas treatment system is operating.

i "1

i Y

i O

I

)

l 1

I l

l i

1 l

INSTRUMENYATION l

SEISMIC MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.

APPLICABILITY:

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.

SURVEILLAN'.E REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNC-TIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1.

4.3.7.2.2 Each of the above required seismic monitoring instruments actuated during a seismic event greater than or equal to 0.01g 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 5 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 arid submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, i

frequency spectrum and resultant effect upon unit features important to safety.

4 i

?

HOPE CREEK 3/4 3-68 Amendment No. 19 i

INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION I

3.3.7.3 The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

a.

With one or more of the required meteorological monitoring instrumen-tation channels inoperable for more than 7 days, in lieu of any other report required by Specification 6.9.1, 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 instrumentation to OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

1 SURVEILLANCE REQUIREMENTS 4.3.7.3 Each of the above required meteorological monitoring instrumentation l

channels shall be demonstrated OPERABLE by the performance of *he CHANNEL CHECK i

and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.3-1.

HOPE CREEK 3/4 3-71 Amendment No.

19

TA8LE 3.3.7.3-1 METEOR 0 LOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENTS INSTRUMENT OPERA 8tE.

a.

Wind Speed 1.

Elev. 33 ft.

1 2.

Elev. 150 ft.

I b.

Wind Ofrection 1.

Elev. 30 ft.

I r

2.

Elev. 150 ft.

1 l

c.

Air Temperature Difference 1.

Elev. 150-33 ft.

1 I

l 4

h I'

f i

i i

}

i l

HOPE CREEK 3/4 3 72 l

1 IAh!I 3.3.7.5-1 ACCIDENI MONIT0tlING INSTRUHfNIATION O

~

MINIMUM APPtlCA810 m'

REQUIR[D NUMB [R CHANN[ts OPfRATIONAL INSTRUM[Mi Of CHANNELS OPERA 8LE CONDIIIONS ACTION 1.

Reactor vessel Pressure 2

1 1,2,3 80 l

2.

Reactor Vessel Water Level 2

1 1,2,3 80 l

3.

Suppression Chad er Water Level 2

1 1,2,3 80 4.

Suppression Chamber Water Temperature" 2

2 1,2,3 80 *)

f 5.

Suppression Chamber Pressure 2

1 1,2,3 80

~

6.

Drywell Pressure 2

1 1,2,3 80 7.

Drywell Air Temperatu e 2

1 1,2,3 80 1 8.

Primary Containment Hydrogen /Osygen Concentration Analyzer and Monitor 2

1 1,2,3 80 h 9.

Safety / Relief Valve Position IndicatorsICI l

2/ valva **

1/ valve **

1,2,3 60

10. Drywell Atmosphere Post-Accident Radiation Monitor 2

1 1,2,3 81

11. Morth Plant Vent Radiatten Monitorf 1

1 1,2,3 81

12. South Plant Vent Radiation Monitorf 1

1 1,2,3 81

13. FRYS Vent Radiatten Moniterf 1

1 1,2,3 81 3

14.

PrimaryCoginnentIsolationValvePosition Indication 2/ valve 1/ valve 1,2,3 82 g

a, x

2 y fHigh range noble gas monitors.

-4

Average bulk peel temperatere.

rk g

- Acoustic monitoring and tall pipe temperature.

g,.

(a)5uppression chamber water temperature instrumentation must satisfy t.Se availability requirements specified 3

in Specification 3.6.2.1.

g (b)0 ne channel coaststs of the open limit switch, and the other channel Consists of the closed limit switch.

(c)the acoustic monitor for r013H say sney be inoperable until Septest;er 21, 1987 or until ttwr first forced ta i}

outage of sufficient doration to ef fect repair prior to that date without.spplying the stautdown reluirement

~*

of ACTION 80(a).

O L-Table 3.3.7.5-1 (Continued)

ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 80 -

d.

With the number of OPERABLE accident monitoring instrumentation channels less than the Required Nut.ber 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 SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERA 8LE 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 SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 81 -'

With the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to 4

OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

I a.

Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and b.

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.

ACTION 82 -

a.

With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, verify the valve (s) position by use of alternate indica-tion methods; restore the inoperable channel (s) to OPERABLE status within 30 days or be in at least HOT SHU100WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLO SHUT 00WN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , j

b.

With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERA 8LE requirements of Table 3.3.7.5-1, verify the valve (*) position by use of alternate indication methods; restore the inocerable 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 and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

1 HOPE CREEK 3/4 3-86 Amendment No. 19

i INSTRUMENTATION TRAVERSING IN-CORE PROBE SYSTEM LIMITING CON 0! TION FOR OPERATION 3.3.7.7.

The traversing in-core probe system shall be OPERABLE with:

a.

Five movable detectors, drives and readout equipment to map the core, and b.

Indexing equipment to allow all five detectors to be calibrated in a common location.

APPLICABILITY: When the traversing in-core probe is used for:

a.

Recalibration of the LPRM detectors, and b.*

Monitoring the APLHGR, LHGR, MCPR, or MFLPD.

ACTION:

With the traversing in-core probe system inoperable, suspend use of the system for the above applicable monitoring or calibration functions. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use for the LPRM calibration function.

1 l

l l

0nly the detector (s) in the required measurement location (s) are required to be OPERABLE.

HOPE CREE' 3/4 3-89 Arendment No.19

IN59RUMENTAT10N t10171NG CONDITION FOR OPERATION 3.3.7.8 i

The material originally contained in Section 3/4.3.7.8 was deleted with i

the issuance of the full Power License.

However, to maintain numerical con-tinuity between the succeeding sections and existing station procedural references to those fechnical Specifications Sections, 3/4.3.7.8 has been intentionally left blank.

1 i

i I

NOPE CRttK 3f4 3.g98 Amendment No.10 Sf? 2

Ng7

O o.

l INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CON 0! TION FOR OPERATION 3.3.7.9 The loose part detection system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a.

With one or more loose part detection system channels inoperable for l

more than 30 days, prepare and submit a Special Report to the Commission r

i 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 i

j OPERABLE status, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCEREQUIREMENTS

[

4.3.7.9 Each channel of the loose part detection system shall be demonstrated j

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.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.

CHANNEL CALIBRATION at least once per 18 months.

f i

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i 5

HOPE CREEK 3/4 3-90 Amendment No,19

O INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION p,

LIMITING CONDITION FOR OPERATION 3.3.7.10 The radioactive liquid eff Jent monitoring instrumentation Channels shown in Table 3.3.7.10-1 shall be v.'lRABLE with their Alarm / Trip Setpoints set i

to ensure that the litaits of Specification 3.11.1.1 are not exceeded.

The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE 00SE CALCULATION MANUAL (00CM).

APPLICABILITY:

At all times.

ACTION:

a.

With a radioactive liquid effluent monitortig instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specificat 4n, immediately suspend the release of radioactive liquid effluents wenitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid affluent monitoring instrumentation channels OPERABLE, take the ACTION shown 1

in Table 3.3.7.10-1.

Exert best efforts to return tr.e instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the l

i next Semiannual Radioactive Effluent Release Report pursuant to Spec-ification 6.9.1.7 why this inoperability was not corrected in a timely manner.

c.

The provisiens of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4

4.3.7.10 Each radioactive liquid effluent monitoring instrumentation channel l

l shall be demonstrated OPERABLE by performance of the CHANNEL CHECv., SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.7.10-1.

j i

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l HOPE CREEK 3/4 3-91 Amend. ment No. 19 I

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i HOPE CREEK 3/4 3 92 g nt Np,. 10

TABLE 4.3.7.10 1 (Continued)

TABLE NOTATf 0NS 7

(1) Tne CHANNEL FUNCTIONAL TEST small also demonstrate that automatic inclation of this patn ay anc control room alarm annunciation occur if any of the following conoitions exists:

Instrument indicates measured levels above the Alarm / Trip 5etpoint, or 4.

0.

Circuit failure, or c.

Instrument indicates a downscale failure.

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

Instrument indicates measured levels above the Alarm Setpoint, or a.

b.

Circuit failure, or c.

Instrument indicates a downscale failure.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference ttandards certified by the National Bureau of Standards (N85) or using standards that have been obtained from suppliers that participate in measurement assurance activities with N85.

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

For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration or are NOS traceable shall be used.

CHANNEkCHECKshallConsistofverifyingindICationofflowduringperiods (4) of release.

CHANNEL CHECK shall be nede at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

l l

l HOPE CREEK 3/4 3 95 Amendment No.10 *

$[E

1327

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION f

3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specifications 3.21.2.1 and 3.11.2.6 are not exceeded.

The Alarm / Trip Setpoints of these chcnnels meeting Specification 3.11.2.1 shall be determined and adjusted in acccrdance with the methodology and parameters in the 00CM.

i APPLICABILITY:

As shown in Table 3.3.7.11-1, t

ACTION:

i a.

With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the l

channel inoperable, or change the setpoint so it is acceptably conservative, b.

With less than the minimum number of radiotetive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown f

in Table 3.3.7.11-1.

Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report pursuant i

to Specification 6.9.1.7 why this inoperability was not corrected in a timely manner.

c.

The provisions of Specification 3.0.3 are not applicable.

1 SURVEILLANCE REQUIREMENTS i

4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies i

shown in Table 4.3.7.11-1.

HOPE CREEK 3/4 3-96 Acendment No.19

O INSTRUMENTATION 3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.8 At least one turbine overspeed protection system shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a.

With one turbine control valve, or one main stop valve per high pressure turbine steam lead inoperable and/or with one combined intermediate valve per low pressure turbine steam lead inoperable, restore the inoperable valve (s) to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or close at least one valve in the affected steam lead (s) or isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months isoitte the turbine from the steam supply.

SURVEILLANCE REQUIREMENTS 4.3.8.1 The provisions of Specification 4.0.4 are not applicable.

4.3.8.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Cycling each of the following valves through at least one complete cycle from the running position:

a)

For the overspeed protection control system; 1)

Six low pressure combined intermediate valves b)

For the electrical overspeed trip system and the mechanical overspeed trip system; 1)

Four high pressure main stop valves, and 2)

Six low pressure combined intermediate valves.

HOPE CREEK 3/4 3-103 Ven nen t No. 19

INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) b.

At least once per 31 days by:

1.

Cycling each of the following valves through at least one complete cycle from the running position:

a)

For the overspeed protection control system; 1)

Four high pressure turbine control valves b)

For the electrical overspeed trip system and the mechanical overspeed trip system; 1)

Four high pressure turbine control valves.

c.

At least once per 18 months by performance of a CHANNEL CALIBRATION l

cf the turbine overspeed protection instrumentation.

d.

At least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of all valve seats, disks and stems and verifying no unacceptable flaws or excessive corrosion.

If unacceptable flaws or excessive corrosion are found, all other valves of that type shall be inspected, i

1 I

i i

1 I

l i

i HOPE CREEK 3/4 3-104

0 REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY LIMIT!NG CON 0! TION FOR OPERAT!0N 3,4.8 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICABILITY: OPERATIONAL CON 0!TIONS 1, 2, 3, 4 and 5.

ACTION:

a.

With the structural integrity of any ASME Code Class 1 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) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum tempersture required by NOT considerations.

b.

With th0 structural integrity of any ASME Code Class 2 component (s) t 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 above 200*F.

c.

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

SURVEILLANCE REQUIREMENTS 4.4.8 No requirements other than Specification 4.0.5.

HOPE CREEK 3/4 4-27 A'endMrit No.

19

REACTOR COOLANT SYSTEM

^

3/4.4.9 RESIOUAL HEAT REMOVAL HOT SHUTDOWN LIMITING CON 0! TION FOR OPERATION 3.4.9.1 Two# shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one rectreulation pump is in operation, at least one shutdown cooling mode loop shall be in operation *'##

eith each loop consisting of:

a.

One OPERA 8LE RHR pump, and b.

One OPERA 8LE RHR heat exchanger.

APPLICA81LITY:

OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint.

ACTION:

l a.

With less than the above required kHR shutdown cooling mode loops OPERABLE, immediately initiate corrective action to return the required loops to OPERA 8LE status as soon as possible.

Within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal for each inoperable RHR thutdown cooling mode loop.

Be in at least COLD SHUTDOWN within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .**

b.

With no RHR shutdown cooling mode loop or recirculation pump in operation, l

inmediately initiate corrective action to return at least one loop to operation as soon as possible.

Within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour, c.

The provisions of Specification 3.0.4 are not applicable.

SURVE!LLANCE REQUIREMENTS 4.4.9.1 At least one shutdown cooling mode loop of the residual heat removal system, one recirculation pump, or alternate method shall be determined to be i

i in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for i

0 i

surveiltance testing provided the other loop is OPERA 8LE and in operation or at least one recirculation pump is in operation.

CThe shutdown cooling pump may be removed from operation for up to 2 Paurs per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided the other loop is OPERA 8LE.

1. The RHR shutdown coojing mode loop may be removed from operation during hydrostatic testing.

C*Whenever two or more RHR subsystees are inoperable, if unable to attain COLO SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as s

low as practical by use of alternate heat removal methods.

HOPE CREEK 3/4 4-28

i i

l REACTOR COOLANT SYSTEM COLD SHUT 00WN

(

LIMITING C040! TION FOR OPERATION l

3.4.9.2 Two# shutdown cooling mode loops of the residual heat removal (RHR) f system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation *'##

i j

with each loop consisting of*

a.

One OPERA 8LE RHR pump, and I

i t

b.

One OPERABLE RHR heat exchanger.

i APPLICABILITY: OPERATIONAL CONDITION 4 and heat losses to ambient ** are not l

]

sufficient to maintain OPERATIONAL CON 0! TION 4.

l l

ACTION:

1 i

a.

With less than the above required RHR shutdown cooling mode loops OPERABLE, i

f within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate I

the operability of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling mode loop.

l b.

With no RHR shutdown cooling mode loop cr recirculation pump in operation, j

within one hour establish reactor coolant circulation by an alternate 1

method and monitor reactor coolant temperature and pressure at least once j

per hour, j

SURVEILLANCE REQUIREMENTS l

4.4.9.2 At least one shutdown cooling mode loop of the residual heat removal system, recirculation pump or alternate method shall be determined to be in j

operation snd circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

f

ne RHR shutdown cooling mode loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for

[

0 surveillance testing provided the other loop is OPERA 8LE and in operation or t

i at least one recirculation pump is in operation.

l i

"The shutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per B hour period provided the other loop is OPERABLE.

l l

i

1. The shutdown cooling mode loop may be removed from operation during i

I hydrostatic testing.

l

}

- Ambient losses must be such that no increase in reactor vessel water temper-I l

ature will occur (even though COLD SHUT 00kN conditions are being maintained).

i t

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HOFE CREEK 3/4 4-29 Anendment No. 19

PLANT SYSTEM 5 3/4.7.6 SEALEO SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.6 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.

APPLICABILITY:

At all times.

ACTION:

a l

a.

With a sealed source having removable contamination in excess of the d

above limit, withdraw the sealed source from use and either:

1.

Decentaminate and repair the sealed source, or 2.

Dispose of the sealed source in accordance with Commission Regulations.

d I

b.

The provisions of Specification 3.0.3 are not applicable.

^

i SURVEILtANCE REQUIREMENTS 1

I 4.7.6.1 Test Requirements - Each sealed source shall be tested for leakage l

and/or contamination by:

a.

The licensee, or b.

Other persons specifically authorized by the Connission or an j

Agreement State.

4

]

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample, 4.7.6.2 Test Frequencies Each category of sealed sources, excluding startup tources aiId fission detectors previously subjected to core flux, shall be tested l

at the frequency described below.

a.

Sources in use - At least once per six months for all sealed sources containing radioactive material:

1.

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

{

2.

In any form other than gas.

I l

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HOPE CREEK 3/4 7 19 AN ndrent No.

19

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous six months.

Sealed sources and fission detectors transferred without a certificate indicating the last test date shall be tested prior to being placed into use, c.

.Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days prior to being subjected to core flux or installed in the core and following repair or maintenance to the source.

4.7.6.3 Reports - A report shall be prepared and submitted to the Commission on an annual basis if sealed source or fission detector leakage tests reveal the presence of greater than or equal to 0.005 alcrocuries of removable contamination.

HOPE CREEK 3/4 7-20

REFUELING OPERATIONS 3/4.9.11 RES!OUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode loop of the residual heat removal (RHR) systen shall be OPERA 8LE and in operation

with:

s.

One OPERA 8LE RHR pump, and b.

One OPERA 8LE RNR heat exchanger.

APPLICA8!LITY:

OPERATIONAL CON 0! TION 5, when irradiated fuel is in the reactor i

vessel and the water level is greater than or equal to 22 feet 2 inches above the top of the reactor pressure vessel flange and heat losses to ambient ** are l

not sufficient to maintain OPERATIONAL CONDITION 5.

ACTION:

a.

With no RHR shutdown cooling mode loop OPERA 8LE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter, demonstrate the operability of at least one alternate method capable of decay heat removal.

Othe rwi se, suspend all operations involving an increase in the reactor decay heat load and establish SECONDARY CONTAINMENT INTEGRITY within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , b.

With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.

SURVEILLANCE REQUIPEMENTS 4.9.11.1 At least one shutdown cooling mode loop of the residual heat removal 4

systee or alternate method shall be verified to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

f l

e i

i The shutdown cooling pump may be removed froe operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8-hour period.

- Ambient losses must be such that no increase in reactor vessel water temper-ature will occur (even though REFUELING conditions are being maintained).

HOPE CREEK 3/4 9-17

REFUELING OPERATIONS LOW WATER LEVEL LIMITING ;3NDIT!0N FOR OPERATION 3.9.11.2 Two shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and at least one loop shall be in operation," with each loop consisting of:

4 a.

One OPERABLE RHR pump, and b.

One OPERABLE RHR heat exchanger.

APPLICABILITY: OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is less tnan 22 feet 2 inches above the top of the reactor pressure vessel flange and heat losses to ambient ** are not sufficient to maintain OPERATIONAL CONDITION 5.

ACTION:

a.

With less than the above required shutdown cooling mode loops of the RHR l

system OPERABLE, within one hour and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months there-i after, demonstrate the OPERABILITY of at least one alternate method capable of decay heat removal for each inoperable RHR shutdown cooling i

mode loop.

i j

b.

With no RHR shutdown cooling mode loop in operation, within one hour establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature at least once per hour.

f SURVEILLANCE REQUIREHENTS i

P 4.9.11.2 At least one shutdown cooling mode loop of the residual heat removal l

system or alternate method shall be verified to be in operation and circulating i

reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l

[

I t

l "The snutdown cooling pump may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months i

i per 8-hour period.

C* Ambient losses must be such that no increase in reactor vessel water temper-ature will occur (even though REFUELING conditions are being maintained).

HOPE CREEK 3/4 9 18 Ae4ndment No. 19

RA010 ACTIVE EFFLUENTS DOSE LIMIT!NG CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEM8ER OF THE PUBLIC from radio-active materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.1-1) shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mress to any organ, and b.

During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

HOPE CREEK 3/4 11-5 Am nd ent No. 19

RADI0 ACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CON 0! TION FOR OPERATION

(

1 i

3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appropriate l

portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.1 1) would exceed 0.06 arem to the total body or 0.2 mrem to any i

organ in any 31 day period.

APPLICABILITY:

At all times.

I ACTION:

i a.

With radioactive liquid waste being discharged and in excess of the above limits.and any portion of the licuid radwaste treatment system j

not in operation, prepare ard submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the

[

following information:

l 1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or suo-i systems, and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and i

3.

Summary description of action (s) taken to prevent a recurrence.

l b.

The provisions of Specification 3.0.3 are not applicable.

SURVE!LLANCE REQUIREMENTS

[

4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM.

l 4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting Specifications 3.11.'.1 and 3.11.1.2.

i i

I HOPE CREEK 3/4 11-6 A endment No.19

l RADI0 ACTIVE EFFLUENTS j

LIQUIO HOLOUP TANKS LIMITING CON 0! TION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above tanks exceeding the above limit, imediately suspend all additions of radicactive 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 Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.

b.

The provisions of Specification 3.0.3 are not applicable.

l l

SURVE!LLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contaired in each of the above tanks shall be determined to be within the above limit by analyzing a repre-sentative sample of the tank's contents at least once per 7 days when radio-active materials are being added to the tank.

HOPE CREEK 3/4 11-7 Am n eent No. 19

RADI0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate due to radioactive m.terials released in gaseous effluents from the site to areas at and beyoi.d the SITE BOUNDARY (see Figure 5.1.1-1) shall be limited to the following:

a.

For noble gases:

Less than or equal to 500 arems/yr to the total body and less than or equal to 3000 aress/yr to the skin, and b.

For iodine-131, iodine-131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days:

Less than or equal to 1500 arems/yr to any organ.

APPLICABILITY:

At all times.

ACTION:

With the dose cate(s) exceeding the above limits, immediately restore the release rate to within the above limit (s).

SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limitt in accordance with the methodology and parameters in the 00CM.

4.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium, and all radio-nuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be witnin the above limits in accordance with the methodology and parameters in the 00CM by obtaining reprer ntative samples and performing analyses in accordance with the sampling and analysis progrsa specified in Table 4.11.2.1.2-1.

l Mb?E CREEK 3/4 11-8

TA8LE 4.11.2.1.2-1 (Continued)

TABLE NOTATIONS (b)The principal gamma emitters for which the LLO specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases.

This list does not mean that only these nuclides are to be sensidered.

Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7.

(c) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period.

This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 conce.itration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

(d) Tritium grab samplec shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.

(e)The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(f) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler.

Sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10.

l This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

l l

HOPE CREEK 3/4 11-11 i

O RADI0 ACTIVE EFFLUENTS DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) shall be liaited to the following:

a.

During any calendar quarter:

Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation and, b.

During any calendar year:

Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY:

At all times.

ACTION a.

With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Ren rt that identifies the cause(s) for exceeding the limit (s) and deft-whe corrective actions that have been taken to reduce the reles_

and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

HOPE CREEK 3/4 11-12 Amendment No. 19

RADI0 ACTIVE EFFLUENTS DOSE - IODINE-131, IODINE-133. TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION s

3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iciine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef fluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) shall be limited to the following:

a.

During any calendar quarter:

Less than or equal to 7.5 mrems to any organ and, b.

During any calendar year:

less than or equal to 15 mrems to any organ.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that identifies the cause(s)

L l

for exceeding the limit and definus the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.

HOPE CREEK 3/4 11-13 Amendment No.19

RADI0 ACTIVE EFFLUENTS GASE0US RA0 WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The GASEOUS RA0 WASTE TREATMENT SYSTEM shall be in operation.

APPLICABILITY: Whenever the main condenser steam jet air ejector system is in operation.

ACTION:

a.

With gaseous radwaste from the main condenser air ejector system being discharged without treatment for more than 7 days, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report that includes the following information:

1.

Identification of the inoperable equipment or subsystems and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and '

3.-

Summary description of action (s) taken to prevent a recurrence, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The readings of the relevant instruments shall be checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the main condenser air ejector is in use to ensure that the gaseous radwaste treatment system is functioning.

l l

l I

HOPE CREEK 3/4 11-14 Amendment No. 19

o o O RADI0 ACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM for the Reactor Building and the Service and Radwaste Building shall be OPERABLE and appropriate por-tions of this system shall be used to reduce release of radioactivity when the projected doses in 31 days due to gaseous effluent releases from each unit to areas at and beyond the SITE BOUNDARY (see Figure 5.1.1-1) would exceed:

a.

0.2 mrad to air from gamma radiation, or b.

0.4 mrad to air from beta radiation, or c.

0.3 mrem to any organ of a MEMBER OF THE PUBLIC APPLICABILITY:

At all times.

ACTION:

a.

With radioactive ventilation exhaust being discharged without treat-ment and in excess of the above limits, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Peport that includes the following information:

1.

Identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and l

3.

Summary description of action (s) taken to prevent a recurrence, b.

The provisions of Specification 3.0.3 are not applicable.

l i

l SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM, when the VENTILATION EXHAUST TREATMENT SYSTEM is not being fully utilized.

4.11.2.5.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM shall be con-sidered OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 and 3.11.2.3.

HOPE CREEK 3/4 11-15 Amendment No. 19

o RADIOACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be limited to less than or equal to 4% by volume.

APPLICABILITY:

At all times.

ACTION:

a.

With the concentration of hydrogen in the main condenser offgas treatment system exceeding the limit, restore the concentration to within the limit within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , b.

With continuous monitors inoperable, operation of the main condenser offgas treatment system may continue for up to 30 days provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of hydrogen in the main condenser offgas treatment system shall be determined to be within the above limits by continuously moni-toring the waste gases in the main condenser offgas treatment system whenever the main condenser evacuation system is in operation with the hydrogen monitors required OPERABLE by Table 3.3.7.11-1 of Specification 3.3.7.11.

HOPE CREEK 3/4 11-16 Amendment No. 19 i

RADI0 ACTIVE EFFLUENTS MAIN CONDENSER LIMITING C0H0! TION FOR OPERATION s

3.11.2.7 The radioactivity rate of noble gases measured at the rpcombiner af ter-condenser discharge shall be limited to less than or equal to 330 milli-curies /sec after 30 minute decay.

APPLICA8ILITY:

OPERATIONAL CONDITIONS 1, 2* and 3*.

ACTION:

With the radioactivity rate of noble gases at the recombiner after-condenser discharge exceeding 330 millicuries /sec after 30 minute decay, restore the radioactivity rate to within its ifait within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STAN08Y within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.11.2.7.1 The radioactivity rate of noble gases at the recombiner after-condenser discharge shall be continuously monitored in accordance with Speciff-cation 3.3.7.1.

~

4.11.2.7.2 The radioactivity rate of noble gases from the recombiner after-condenser discharge shall be determined to be within the limits of Specifica-tion 3.11.2.7 at the following frequencies by performing an isotopic analysis of a representative sample of gases taken near the discharge of the main con-denser air ejector:

a.

At least once per 31 days, b.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following an increase, as indicated by the Offgas Radioactivity Monitor, of greater than 50%, after factoring out increases due to changes in THERMAL POWER level, in the nominal stairstate fission gas release from the primary coolant.

c.

The provision

.? Spe-ification 4.0.4 are not applicable.

l l

"when the main condenser air ejector is in operation, i

HOPE CREEX 3/4 11-17

O RADIOACTIVE EFFLUENTS VENTING OR PURGING LIMITING CONDITION FOR OPERATION 3.11.2.8 VENTING or PURGING of the Mark I containment drywell shall be through either the reactor building ventilation system or the filtration, recirculation and ventilation system.

APPLICABILITY:

Whenever the containment is vented or purged.

ACTION:

a.

With the requirements of the above specification not satisfieci, suspend all VENTING and PURGING of the drywell.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.8 The containment shall be determined to be aligned for VENTING or PURGING through either the reactor building ventilation system or the filtration, recirculation and ventilation system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of the drywell.

HOPE CREEK 3/4 11-18 Amer.dtrent No. 19

0 o.

RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.3 Radioactive wastes shall be 50LIDIFIE0 or dewatered in accordance with the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY:

At all times.

ACTION:

a.

With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the solid waste system as necessary to prevent recurrence, b.

With SOLIr.T.FICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, (1) demonstrate by test or analysis that the improperly processed waste in each container meets the requirements for transportation to the disposal site and for receipt at the disposal site and (2) take appropriate administrative action to prevent recurrence.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3.1 The PROCESS CONTROL PROGRAM shall be followed to verify that the pro-perties of the packaged waste meet the minimum stability requirements of 10 CFR Part 61 and other requirements for transportation to the disposal site and re-ceipt at the disposal site.

4.11.3.2 The PROCESS CONTROL PROGRAM shall include sufficient quality control and assurance methods to assure the solidified waste product from any process (either in-house or contracted vendor) meets the requirements for transporta-tion and receipt at the disposal site.

HOPE CREEK 3/4 11-19 Amendment No. 19

RADI0 ACTIVE EFFLUENTS 3/4.11.4 TOTAL 00SE LIMITING CONDITION FOR OPERATION 3.11.4 The annual (ctlendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY:

At all times.

ACTION:

a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifi-cation 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a., or 3.11.2.3b., calculations should be made including direct radiation contributions from the units including outside storage tanks, etc.

to determine whether the above limits of Specification 3.11.4 have been exceeded.

If such is the case, prepare and submit to the Com-mission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce sub-sequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits.

This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report.

It shall also de-scribe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations.

If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a vari-ance in accordance with the provisions of 40 CFR Part 190.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete, b.

The provisions of Specification 3.0.3 are r.ot applicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid end gaseous effluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology and parameters in the 00CM.

4.11.4.2 Cumulative dose contributions from direct radiation from the units including outside storage tanks, etc. shall be determined in accordance with the methodology and parameters in the 00CM.

This requirement is applicable only under conditions set forth in Specification 3.11.4, ACTION a.

HOPE CREEK 3/4 11-20 Amendment No. 19

3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.

APPLICABILITY:

At all times.

ACTION:

a.

With the radiological environmental monitoring program not being conducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in ths Annual Radiological Environmental Operating Report required by Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b.

With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table 3.12.1-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2,(a.Special Report that identifies the cause(s) for exceeding the limit s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

to A MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3.

When more than one of the radionuclidas in Table 3.12.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) concentration (2)

+

...)

1. 0 reporting level (1) reporting level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

to A MEMdER OF THE PUBLIC from all radio-nuclides is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3.

This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.

c.

With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 3.12.1-1, identify specific locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

"The methodology used te estimate the potential annual dose to a MEM6ER OF THE L

PUBLIC shall be indicated in this report.

HOPE CREEK 3/4 12-1

RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDIT:0N FOR OPERATION (Continued)

ACTION:

(Continued)

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Specifica-tion 6.9.1.8, identify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report pursuant to Speci-I fication 6.9.1.8 and also include in the report a revised figure (s) l and table for the 00CM reflecting the new location (s).

d.

The provisions of Specification 3.0.3 are not applicable.

l l

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samnles shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the tal'le and figure (s) in the ODCM, and shall be analyzed purcuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.

l l

HOPE CREEK 3/4 12-2 Amendment No. 19

RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden

of greater than 50 m2 2

(500 ft ) producing broad leaf vegetation.

APPLICABILITY:

At all times.

ACTION:

a.

With a land use census identifying a location (s) that yields a calcu-lated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.

b.

With a land use census identifying a location (s) that yields a calculated dose or dose commicment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) to the radiological environmental monitoring program within 30 days.

The sampling location (s), excluding the control station location, having the lowest calculated dose or dose ccmitment(s), via the same exposure pathway, may be deleted from this monitoring program af ter October 31 of the year in which this land use census was conducted.

Pursuant to Specification 6.9.1.8, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the OOCH reflecting the new location (s).

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities.

The r+sults of the land use census shall be included in the Annual Aadiological Environmental Operating Report pursuant to Specification 6.9.1.6.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted 0/Qs in lieu of the garden census.

Specifications for broad leaf vegetation sampling in Table 3.12.1-1, Part 4.c., shall be followed, including analysis of control samples.

HOPE CREEK 3/4 12-13 Amendment No. 19

-RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMFARISON PROGRAM LIMITING CONDITION FOR OPERATICN

[

3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interleboratory Comparison Program that has been approved by the Commission.

APPLICABILITY:

At all timer.

ACTION:

a.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission

'in the Annual Radiologic:1 Environmental Operating Report pursuant i

to Specification 6.9.1.6.

~

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.

A summary of the results obtained as part of the above required Inter-laboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Spe-ification 6.9.1.6.

r HOPE CREEK 3/4 12-14 Amendment No.19 l

3/4.0 APPLICABILITY BASES Specifications 3.0.1 through 3.0.4 establish the general requirements applicable to Limiting Conditions for Operation.

These requirements are based on the requirements for Limiting Conditions for Operation stated in t..e Code of Federal Regulations, 10 CFR 50.36(r)(2):

"Limiting conditions for operation are the lo' vest functional capability or performance levels of equipment required for safe operation of the facility.

When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

Specification 3.0.1 establishes the Applicability statement within each Individual specification as the requirement for when (i.e., in which OPERATIONAL CONDITIONS or other specified condition =) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.

The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met.

It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or component (s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

There are two basic tjpes of ACTION requirements.

The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements.

In this case, conformance to the ACTION requirements provides an acceptable levol of safety for unlimited continued operation as long as the ACTION requirements continue to be met.

The second type of ACTION requirement specifies a time limit in whi-h conformance to the conditions of the Limiting Condition for i

Operation must be met.

This time limit is the allowable outage time to restore an inoperable system or component to CPERA8LE status or for restoring parameters within specified limits.

If these actions are not conpleted within the allow-able outage time limits, a shutdown is required to place the facility in an OPERATIONAL C0h0! TION or other specified condition in which the specification no longer applies.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met.

The time limits of the ACTION requirements are also applicable when a system or component is removed fo m service for surveillence testing or investigation of operational problems.

Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when i

equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance has not been completed.

When a shutd sn is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new specification becomes applicable.

In this case, the HOPE CREEK B 3/4 0-1 Amendment No. 19

3/4.0 APPLICABILITY BASES (Con't) time limits of the ACTION requirements would apply from the point in time that 4

the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Specification 3.0.2 establishes that noncompliance with a specification exists then the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval.

The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance

}

with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

1 Specification ? 0.3 establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not met and the condi-l tion is not specifically addressed by the associated ACTION requirements.

The I

purpose of this specification is to delineate the time limits for placing the f

unit in a safe shutdown CONDITION when plant operation cannot be maintained within the limits for Safe operation defined by the Limiting Conditions for i

Operatinn and its ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary re.aoval of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation.

This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid.

The time limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE.

This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remedial measures penitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown cay be terminated.

The time limits of the ACTION requiremente are applicable from the point in time there was a failure to meet a Limiting Condition for Operation.

Therefore, the shutdown may be terminated if the ACTION raquire-ments have been met or the time limits of th6 ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in COLD SHUT 00VN when a shutdown is required during POWFA operation.

If the plant is in a lower CONDITION of operation when a shutdown is required, the time limit for reaching the next lower CONDITION of operation applies.

However, if HOPE CREEK B 3/4 0-2 Anendment No. 19

- -- - - _- -_---- J

3/4.0 APPLICABILITY BASES (Con't) a lower CONDITION of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTOOWN, or other OPERATIONAL CONDITION, is not reduced.

For example, if STARTUP is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach HOT SHUTOOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time to reach HOT SHUTOOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if remedial measures are completed that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower CONDITION of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into an OPERATIONAL, CONDITION or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met.

If the new specification becomes appli-

~

cable in less time than specified, the difference may be added to the allowable outage time limits of the second specification.

However, the allowable outage time limits of ACTION requirements for a higher CONDITION of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower CONDITION of operation.

The shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification '.0.4 establishes limitations on a change in OPERATIONAL CONDI-TIONS when a Limiting Condition for Operation is not met.

It precludes placing the facility in a higher CONDITION of 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 require-ments if a change in CONDITIONS were permitted.

The purpose of this specifi-cation is to ensure that facility operation is not initiated or that higher CON 0!TIONS 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 af ter a change in OPERATIONAL CONDITIONS.

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

The provisions of this specification should not, however, be inter-preted 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 plar.ing the facility in a lower CONDITION of operation.

HOPE CREEK B 3/4 0 3 Arendment No. 19

3/4.0 APPLICABILITY BASES (Con't)

Specifications 4.0.1 through 4.0.5 establish the general requirements appli-cable to Surveillance Requirements.

These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is Caintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.

The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Liciting Conditions fcr Operation are applicable.

Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not apply unless ctherwise specified.

The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended.

Item a. permits an allowable extension of the normal surveillance interval to facilitate surveil-lance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

Item b. limits the use of the provisions of item a, to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified.

The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most pro-bable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.

These provisions are suf-ficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveil-lance interval.

Specification 4.0.3 establishes the failure to perform a Surveillance Require-ment within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requ'.rements have been satisfactorily performed eithin the specified time interval.

However, nothing in this provision is to HOPE CREEK B 3/4 0-4 Amendment No.

19

o.

3/4.0 APPLICABILITY BASES (Con't) be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Require-ments.

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION require-ments apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveil-lance interval, defined by the provisions of Specification 4.0.2, was a viola-tion of the OPERABILITY requirements of a limiting Condition for Operation that is subject to enforcement action.

Further, the failure to perform a surveil-lance within the provisions of Specification 4.0.2 is a violation of a Techni-cal Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(i)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3., a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements.

This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.

Specification 4.0.4 establishes the requirement that all applicable surveil-lances must be met before entry into an OPERATIONAL CONDITION or other I

HOPE CREEK B 3/4 0-5 Amendment No. 19

9 0 3/4.0 APPLICABILITY BASES (Con't) 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 an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL CONDITIONS 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 assume that the Limiting Conditions for Operation are met during initial plant startup or following a plant outage.

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

Specification 4.0.5 establishes the requirement that inservice inspection of X5HE 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 a periodically updated version of Section XI of tne ASME Boiler and Pressuro Vessel Code and Addenda as required by 10 CTR 50.55a.

These requirements apply except when relief has been provided in writing by the Commission.

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 clarifica-tion is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequen-cies for performing the required inservice lnspection 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.

The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL CONDITION or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision that allows pumps and valves to be tested up to one week after return to normal operation.

The Technical Specification definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision that 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.

HOPE CREEK B 3/4 0-6 Amendment No. 19

ML20155F290

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