Text

Amend 10 to License NPF-57,revising Numbering of Certain Tech Spec Sections
	ML20237L361
Person / Time
Site:	Hope Creek
Issue date:	09/01/1987
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20237L364	List: ML20237L361; ML20237L368;
References
	NUDOCS 8709080369
	Download: ML20237L361 (23)
	v • d • e

_ _ _ _

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NUCLE AR REGULATORY COMMISSION e-o f

WAwNcTow, o. c. 20sss PURLif SERVICE EL'ECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-354 HOPE CREEK GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.10 License No. NPF-57 L

1.

The Nuclear Regulatory Comission (the Comission or the NPC) has found that:

The application for amendment filed by the Public Service Ele:tric &

A..

Gas Company (PSE8G) dated May 1, 1987, 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 provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFP 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 Comission'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) Techr.ical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.10, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

PSE&G shall operate the facility ir accordance with the Technical Specifications and the Environmental Protection Plan.

8709000369 070901 PDR ADOCK 05000354 P-PDR

. 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

Attachment:

Changes to the Technical Specifications

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Date of Issuance: Septenber 1,1987 l

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

FOR THE NUCLEAR REGULATORY COMMISSION ~

AN

' alter R. Butler, Director

' Project Directorate I-2 Division of Reactor Projects I/II.

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Attachment:

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' Changes to the Technical i

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Date of Issuance: September 1, 1987 i

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-ATTACHMENT TO LICENSE AMENDMENT NO. 10 FACILITY OPERATING LICENSE NO. NPF-57 T

DOCKET N0. 50-354

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Peplace the following pages'of the Appendix "A" Technical Specifications with the attached pages.. The revised pages are identified by Amendment n_ umber and contain vertical' lines indicating the area of change.. Overleaf pages provided to maintain, document completeness.*

Remove Insert 3/4 3-89*'

3/4 3-89*

.3/4 3-89a 3/4 3-90 3/4 3-90 3/4 3-91 3/4 3-91 3/4 3-92 3/4 3-92 3/4'3-93 3/4 3-93 3/4 3-94' 3/4 3-94

.3/4 3-95 3/4 3-95 3/4 3-96 3/4 3-96 3/4 3-97 3/4 3-97 3/4 3-98 3/4.3-98 3/4 3-99 3/4 3-99 3/4 3-100-3/4 3-100 3/4 3-101 3/4 3-101 3/4 3-102-3/4 3-102 3/4 11-15*

3/4 11-15*

3/4 11-16 3/4 11-16 B 3/4 3-5*

B 3/4 3-5*

B 3/4 3-6 B 3/4 3-6 l

INSTRUMENTATION TRAVERSING IN-CORE PROBE SYSTEM L1HITING CONDITION FOR OPERATION l

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.

i 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 Specifications 3.0.3 and 3.0.4 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.

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l "Only the detector (s) in the required measurement location (s) are required to be OPERABLE.

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. r, The material originally contained in Section 3/4. 3'.7.cl was deleted with j c.,

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the issuance of the Full Power License. ' Howefer, to. maintain numerical con-tinuity'betweenthesucceedingsectionsandexistingstationprocedural/\\

references to those Technical Specifications Sections, 3/4.3.7.8.has beerf

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cause?of the malfunction.and the p1pns for restoring the channel (s) to 1

c.:t OPERABLEi. status.

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5_ SURVEILLANCE REQUIREMENTS 4.3.7.9 Each channel' of the 1)ose part detection system "skall.be demonstrated.-l OPERABLE by pe'rformance of a,,'.

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CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

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CHANNEL FUNCTIONAL TEST at least;gnce per 31 days,'and.

CHANNELLCALIBRATIONatleastonceper18 months.

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HOPE CREEK 3/4 3-90 Amendment No. 10 V,

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. INSTRUME NTATION.

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDil10N FOR OPERA 110N 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown:in Table 3.3.7.10-1 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits'of Specification 3.11.1.1 are not exceeded.

The Alarm / Trip Setpoints of these channels sh'all be determ'ined and adjusted in accordance with the methodology.and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY:

At all times.

l ACTION:

.With a radioactive liquid effluent monitoring instrumentation channel a.

Alarm / Trip 5etpoint less conservative than required by the above specification, immediately suspend the release of radioact',a liquid l

effluents monitored by.the affected channel, or declare the channel inoperable, or, change the setpoint so it is acceptably conservative.

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b.

With less; than the minimum number of radioactive liquid effluent monitoring instrumentation channels'0PERABLE take the ACTION shown in Table 3.3.7.10-1.

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

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

manner,

-The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.7.10.Each radioactive liquid effluent monitoring instrumentation channel l

shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE j

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.7.10-1.

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ACTION 110 -

With the. number of channels OPERABLE less than required by the

, PNP Minimum Channels OPERABLE requirement, effluent releases via this M

pathway may continue provided that prior to-initiating a release:

At least two independent samples are analyzed in.accordance

-a.

with Specification 4.11.1.1.2, and b'.

At least two technically qualified members of the facility Staff independently verify the release rate calculations and discharge line valving; Otherwise. suspend release of radioactive effluents via this

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pathway.

ACTION 111 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for gross radioactivity 4

at a limit of detection of at least 10 7 microcuries/ml.

Other-g:a-.l-wise, suspend release of radioactive effluents via this pathway.

ACTION 112 -

With the number of channels OPERABLE less than required by the Q i" Minimum Channels OPERABLE requirement, effluent r-leases via L>,I this pathway may continue provided the flow rate is estimated at 3

least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump performance curves generated in place may be used to estimate flow.

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TABLE NOTATIONS

(.1) The. CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room' alarm annunciation occur if any of the following conditions exists:

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

b.

Circuit failure, or c.

Instrument indicates a downscale failure.

(2) The CHANNEL' FUNCTIONAL TEST shall also demonstrate that control room

'alaim annunciation 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 standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NB5.

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 NBS traceable shall be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.

CHANNEL CHECK shall be made 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.

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HOPE CREEK 3/4 3-95 Amendment No,10 ~

lNSTRUMENTAT10N RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTAL 10N LIMITING CONDITION FOR OPERATION c

3.3.7.11.The radioactive gaseous effluent monitoring instrumentation channi 's shown in Table 3.3.7.11-1 shall be OPERABLE with their Alarm / Trip Setpoints,et to ensure that the limits of Specifications 3.3L 2.1 and 3.11.2.6 are not exceeded.

The Alarm / Trip Setpoints of these channels meeting Specification 3.1L2.1 shall be dettemined and adjusted in accordance with the methodology and parameters in the L?CM.

APPLICABILITY:

As shown in Table 3.3.7.11-1.

l ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less co'nservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents. monitored 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 gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.

Exert best efforts to return the instruments j

to OPERABLE status within 30 days and, if unsuccessful, explain in the next Semiannual R>dioactive Effluent Release Report pursuant to Specification 6.9.1.7 why this inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel l shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3.7.11-1.

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TABLE NOTATION At all times.

- During operation of the main condenser air ejector.

ACTION 122 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Otherwise, suspend release of radio-active effluents via this pathway.

ACTION 123 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Otherwise, suspend release of radio-active effluents via this pathway.

ACTION 124 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of main condenser offgas treatment system may continue 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 fol-lowing 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Otherwise, suspend release of radioactive ef-fluents via this pathway.

ACTION 125 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.2-1.

HOPE CREEK 3/4 3-99 Amendment No. 10

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TABLE 4.3.7.11-1 (Continued)

TABLE NOTATION

At all times.

During operation of the main condenser air ejector.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room l

alarm annunciation occurs if any of the following conditions exists:

l 1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

1 l

3.

Instrument indicates a downscale failure.

The initial CHANNEL CALIBRATION shall be performed using one or more of (2) the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.

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 NBS traceable shall be used.

(3) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1.

Zero volume percent hydrogen, balance nitrogen, and 2.

1.5 volume percent hydrogen, balance nitrogen.

HOPE CREEK 3/4 3-102 Amendment No, 10

RADI0 ACTIVE EFFLUENTS VENTILA110N 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:

With radioactive ventilation exhaust being discharged without treat-a.

ment and in excess of the above limits, preparc and submit.to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report 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 3.

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

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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-q sidered OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 and 3.11.2.3.

l 1

l HOPE CREEK 3/4 11-15

l I

RADIOACTIVE EFFLUENTS EXPLO51VE GAS FIXTURE 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:

With the concentration of hydrogen in the main condenser offgas a.

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 ,

)

With continuous monitors inoperable, operation of the main condenser b.

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 .

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS The concentration of hydrogen in the main condenser offgas treatment 4.11.2.6 system shall be determined to be within the above limits by continuously moni-toring the waste gases in the main condenser offges 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.

1

3

[;

i 4

I I

L.,

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l

. INSTRUMENTATION

]

l-BASES MONITORING INSTRUMENTATION (Continued)

I radioactive materials to the atmosphere.

This capability is required to evaluate the need for initiating protective measures to p*otect.the health and.

safety of the pub'lic.

This. instrumentation is consistent with the recommenda-tions of Regulatory Guide 1.23 "0nsite Meteorological Programs," February, 1972.

3/4.3.7.4-REMOTE SHUTDOWN MONITORING INSTRUMENTATION AND CONTROLS 1

The OPERABILITY of the remote shutdown monitoring instrumentation and con-trols ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control This capability is required in the event control room habitability is room.

lost and is consistent with General Design Criteria 19 of 10 CFR 50.

]

)

3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION I

The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident.

This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980, i

l 3/4.3.7.6 SOURCE RANGE MONITORS l

The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown.

At these power levels, reactivity additions shall not be made without this flux level information available to the operator.

When the inter-mediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.

3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial neutron flux distribution of the reactor core.

HOPE CREEK B 3/4 3-5 l

.h INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.8 The material l originally contained in 5ection 3'/4.3.7.8 was deleted with

~

the issuance of the Full Power License.

However, to maintain numerical con-tinuity between the succeeding sections and existing station procedural

- references to those Technical Specifications Sections, 3/4.3.7.8 has been intentionally left blank.

3/4.3.7.9 LOOSE-PART DETECTION SYSTEM h

The OPERABILITY of~the loose part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.

The allowable out-of-service times and surveillance requirements are consistent with the recce mendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.

3/4.3.7.10 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l

The radioactive liquid effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liqu'id effluents during actual or potential releases of liquid effluents.

The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the j

alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.7.11 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent monitoring instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM.

This will ensure the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20.

'This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the main condenser offgas treatment system.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3 HOPE CREEK B 3/4 3-6 Amendment No. 10

_ _ _j

ML20237L361

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