ML20044E413

Proposed Tech Specs Re Fire Protection

ML20044E413
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/17/1993
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20044E412	List: B14426, Application for Amend to License DPR-61,revising TS & License Condition Re Fire Protection,Per GL 86-10 ML20044E413
References
NUDOCS 9305240323
Download: ML20044E413 (68)

Text

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Docket No. 50-213 B14426 1

Haddam Neck Plant Proposed Revision to Technical Specifications l'

j t

l May 1993 9305240323 930517 PDR ADDCK 05000213 PDR p

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PME i

1 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0lNTS.....................

3/4 3-19 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........

3/4 3-21 4

3/4.3.3 MONITORING INSTRUMENTATION.........................

3/4 3-23 TABLE 3.3-4 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS.........................................

3/4 3-24 i

TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT j

OPERATIONS SURVEILLANCE REQUIREMENTS...............

3/4 3-25 Movabl e Incore Detectors........................... 3/4 3-26 Seismic Instrumentation............................

3/4 3-27 i

TABLE 3.3-5 SEISMIC MONITORING INSTRUMENTATION.................

3/4 3-28 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION l

SURVEILLANCE REQUIREMENTS..........................

3/4 3-29 I

Meteorlogical Instrumentation...................... 3/4 3-30 t

TABLE 3.3-6 METEORLOGICAL MONITORING INSTRUMENTATION...........

3/4 3-31 j

TABLE 4.3-5 METEORLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........................

3/4 3-32 Accident Monitoring Instrumentation................

3/4 3-33 TABLE 3.3-7 ACCIDENT MONITORING INSTRUMENTATION................

3/4 3-34 TABLE 4.3-6 ACCIDENT MONITORING INSTRUMENTATION j

SURVEILLANCE REQUIREMENTS..........................

3/4 3-38 l

TABLE 3.3-8 DELETED Radioactive Liquid Effluent Monitoring 3

Instrumentation....................................

3/4 3-44 TABLE 3.3-9 RADI0 ACTIVE LIQUID EFFLUENT MONITORING t

INSTRUMENTATION....................................

3/4 3-45 i

TABLE 4.3-7 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........

3/4 3-47

'l Radioactive Gaseous Effluent Monitoring Instrumentation....................................

3/4 3-49 HADDAM NECK VI Amendment No. J U,

0145

-t INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS SECTION PAGE TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..........................

3/4 7-6 Main Steam Line Trip Valves.............................

3/4 7-7 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.........

3/4 7-8 3/4.7.3 SERVICE WATER SYSTEM....................................

3/4 7-9 3/4.7.4 SNUBBERS................................................

3/4 7-10 j

TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL....................

3/4 7-10a 3/4.7.5 SEALED SOURCE CONTAMINATION.............................

3/4 7-14 3/4.7.6 DELETED TABLE 3.7-4 DELETED TABLE 3.7-5 DELETED 3/4.7.7 DELETED 3/4.7.8 DELETED 3/4.7.9 FEEDWATER ISOLATION VALVES..............................

3/4 7-31 TABLE 3.7-6 FEEDWATER ISOLATION VALVES...........................

3/4 7-32 l

3/4.7.10 EXTERNAL FLOOD PROTECTION...............................

3/4 7-33 1

3/4.7.11 PRIMARY AUXILIARY BUILDING AIR CLEANUP SYSTEM...........

3/4 7-34 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES i

0perating...............................................

3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE.......................

3/4 8-6 i

Shutdown................................................

3/4 8-7 3/4.8.2 D.C. SOURCES 0perating...............................................

3/4 8-8_

TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS....................

3/4 8-10 Shutdown................................................

3/4 8-11 i

4 HADDAM NECK X

Amendment No. J/J, JJJ, 0146

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INDEX i

BASES SECTION PAGE 3/4.4.7 CHEMISTRY..............................................

B 3/4 4-7

[

3/4.4.8 SPECIFIC ACTIVITY......................................

B 3/4 4-7 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................

B 3/4 4-8 3/4.4.10 STRUCTURAL INTEGRITY...................................

B 3/4 4-12 3/4.4.11 REACTOR COOLANT SYSTEM VENTS...........................

B 3/4 4-12 i

P 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 & 3/4.5.2 ECCS SUBSYSTEMS................................

B 3/4 5-1 3/4.5.3 REFUELING WATER STORAGE TANK...........................

B 3/4 5-2 3/4.5.4 pH CONTROL SYSTEM......................................

B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.....................................

B 3/4 6-1 3/4.6.2 CONTAINMENT AIR RECIRCULATION SYSTEM....................

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES............................

B 3/4 6-3 i

r 3/4.7 PLANT SYSTEMS 1

3/4.7.1 TURBINE CYCLE...........................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.........

B 3/4 7-2 3/4.7.3 SERVICE WATER SYSTEM....................................

B 3/4 7-2 3/4.7.4 SNUBBERS................................................

B 3/4 7-3 3/4.7.5 SEALED SOURCE CONTAMINATION.............................

B 3/4 7-4 t

3/4.7.6 DELETED 3/4.7.7 DELETED 3/4.7.8 DELETED 3/4.7.9 FEEDWATER ISOLATION VALVES..............................

B 3/4 7-6 j

3/4.7.10 EXTERNAL FLOOD PROTECTION...............................

B 3/4 7-6 3/4.7.11 PRIMARY AUXILIARY BUILDING AIR CLEANUP SYSTEM...........

B 3/4 7-6 j

r HADDAM NECK XIV Amendment No. JEE, 0147 I

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.1

INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS The OPERABILITY of the Containment Atmosphere Gaseous Radioactivity Monitor-ing System ensures that Gaseous Radioactivity Monitoring System will monitor inside containment as a means to detect RCS leakage.

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core.

The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

3/4.3.3.3 SEISMIC INSTRUMENTATION

'i The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to determina the magnitude of a seismic event and evaluate the response of those features important to safety.

This capabili-ty is required to permit comparison of the measured response to that used in the design basis for the facility.

l 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION j

The OPERABILITY of the meteorological instrumentation ensures that suffi-cient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radio-active materials to the atmosphere. This capability is required to evaluate i

the need for initiating protective measures to protect the health and safety I

of the public and is consistent with the recommendations of Regulatory Guide 1.23, "0nsite Meteorological Programs," February 1972.

i 3/4.3.3.5 ACCIDENT MONITORING INSTRUMENTATION i

The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor

~1 and assess these variables following an accident.

This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 3,

" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and following an Accident," May 1983 and NUREG-0737,

" Clarification of TMI Action Plan Requirements," November 1980.

l 3/4.3.3.6 - DELETED HADDAM NECK B 3/4 3-2 Amendment No. J U,

caso i

t INSTRUMENTATION j

BASES 3/4.3.3.7 RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in ligt 1 effluents during actual or potential releases of liquid effluents.

The i

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 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.

l 3/4.3,3.8 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent 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 REM 0DCM to ensure

{

that the alarm / trip will occur prior to exceeding the limits of r

10 CFR Part 20.

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

3/4.3.3.9 BORON DILUTION ALARM The shutdown monitors provide indication of positive reactivity insertion during operation in Modes 3, 4, 5, and 6.

The indication is credited in the Baron Dilution design basis analysis.

3/4.3.4 FLOODING PROTECTION I

The liquid level instrumentation is provided to monitor liquid levels in areas of potential flooding caused by local pipe ruptures.

The system ensures that early warning will occur so that protective action can be taken L

HADDAM NECK B 3/4 3-3 Amendment No. J U,

(

015D

PLANT SYSTEMS j

i BASES i

3/4.7.4 SNUBBERS (Continued)

The service life is evaluated via manufacturer input and information with consideration of snubber service conditions and associated installation and i

maintenance records (newly installed snubber, seal replaced, spring replaced, in high radiation area, high temperature area, location of potential fluid transient loading, etc.)

The requirement to monitor the snubber service life l

is included to ensure that the snubbers periodically undergo a performance evaluation in view of age and operating conditions.

(Due to implementation of the snubber service life monitoring program after several years of plar.t operation, the historical records to date may be incomplete.)

Snubber service life records will provide a statistical basis for future consideration of snubber service life.

3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for plutonium.

This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a l

source in that group. Those sources which are frequently handled are required to be tested more often than those which are not.

Sealed sources which are l

continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

3/4.7.6 DELETED j

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I PLANT SYSTEMS i

BASES l

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0151 i

ADMfNISTRATIVE CONTROLS P

-c.

An individual qualified in radiation protection procedures

• shall be on site when fuel is in the reactor; d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation; 1

e.

DELETED f.

Administrative procedures shall be developed and implemented to limit the working hours of facility staff who perform safety-related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No. 82-12).

The individual qualified in radiation protection procedures may be less l

than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required position.

l l

e HADDAM NECK 6-2 Amendment No. JEE, JEE, 0153 I

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ADMINISTRATIVE CONTROLS f.

Successful completion of the Thames Valley State Technical College associate's degree in Nuclear Engineering Technology program, provided that the individual was enrolled in the program by October 1, 1987.

2.

Dedi led STA: Must meet the STA training criteria of NUREG-0737, Item s.A.1.1, and have received specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING A retraining and replacement training program for the facility staff shall l

be maintained under the direction of the Nuclear Unit Director and shall meet or exceed the requirements and recommendations. of Section 5.5 of ANSI N18.1-1971 and 10CFR55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.

I 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

FUNCTION t

6.5.1.1 The PORC shall function to advise the Nuclear Station Director on all matters related to nuclear safety.

t COMPOSITION 6.5.1.2 The PORC shall be composed of the:

Chairperson:

Nuclear Station Director Member:

Nuclear Unit Director Member:

Operations Manager Member:

Maintenance Manager Member:

Instrument and Control Manager Member:

Reactor Engineer Member:

Engineering Manager Member:

Nuclear Services Director l

Member:

Plant Quality Services Supervisor Member:

Chemistry Manager Member:

Health Physics Manager Member:

Security Manager i

HADDAM NECK 6-5 Amendment No. JJJ, JJJ, JEE, 0154

t ADMINISTRRTIVE CONTROLS i.

Review of the Security Plan and implementing procedures and shall submit recommended changes to the Chairperson of the Nuclear i

Review Board;

[

t j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairperson of the Nuclear Review Board k.

Review of the Fire Protection Program and Implementing Procedures.

AUTHORITY 6.5.1.7 The PORC shall:

a.

Report to and be advisory to the Nuclear Station Director on those areas of responsibility specified in Section 6.5.1.6(a) through (k);

[

b.

Render determinations in writing to the Nuclear Station Director if any item considered under Specification 6.5.1.6a. through d.,

i above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes an unreviewed safety question or requires a

significant hazards consideration determination.

c.

Provide written notification, meeting minutes may be used for this

purpose, to the Executive Vice President-Nuclear and the Chairperson of the Nuclear Review Board of disagreement between the PORC and the Nuclear Station Director; however, the Nuclear Station Director shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

t RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting that, at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these Technical Specifications.

Copies shall be provided to the Executive Vice President-Huclear and i

Chairperson of the Nuclear Review Board.

6.5.2 NUCLEAR REVIEW BOARD (NRB)

OUALIFICATIONS 6.5.2.1 The minimum qualifications of NRB members are as follows:

r a.

The Chairperson and NRB members shall have:

1.

an academic degree in engineering or physical science field, or hold a senior management position, and

[

2.

a minimum of five years technical experience in their respective field of expertise, and 3.

a minimum of nine (9) years combined academic and technical experience.

HADDAM NECK 6-7 Amendment No. JEE, JEE, 0155 r

e

Docket No. 50-213 B14426 Haddam Neck Plant Proposed Changes to.the Operating License May 1993

. - - = -

(3)

CYAPCO, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources or reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required-l (4)

CYAPC0, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material, without i

restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive l

apparatus or components; and l

(5)

CYAPC0, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear material as may be produced by the operations of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in i

10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of the Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act l

and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions i

specified or incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1825 l

megawatts (thermal).

(2)

Technical Specifications t

The Technical Specifications contained in Appendix A, as revised through Amendment No. 135, are hereby incorporated in the license.

The licensee shall operate the facility in l

accordance with the Technical Specifications.

[(3)

Deleted per Amdt. 29,10-24-78.]

(4)

Fire Protection The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report and as approved in the SER, dated October 3, 1978 and Supplements dated February 6, 1981, November 11, 1981, November 14, 1984, November 27, 1987, January 20,

1990, April 10,

1990, August 14, 1990, June 27, 1991, October 16, 1991 and November 21, 1991 subject to the following provisions.

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

4

4-(5)

Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10CFR73.55 (51FR27817 and 27822) and to the authority of 10CFR50.90 and 10CFR50.54(p).

The plans, which contain Safeguards Information protected under 10CFR73.21, are entitled:

"Haddam Neck Plant Physical Security Plan," with revisions submitted through January 24, 1989; "Haddam Neck Plant Guard Training and Qualification Plan," with revisions submitted through January 27, 1983; and "Haddam Neck Plant Safeguards Contingency Plan," with revisions submitted through January 27, 1983; and "Haddam Neck Plant Safeguards Contingency Plan,"

with revisions submitted through December 9,1983. Changes made in accordance with 10CFR73.55 I

shall be implemented in accordance with the schedule set forth herein.

(6)

Intearated Implementation Schedule a.

The Connecticut Yankee Atomic Power Company shall implement and maintain in effect the Integrated Implementation Schedule Program Plan (the Program Plan) to be followed for scheduling of plant modifications and engineering studies. The Program Plan shall be followed from and after the effective date of this license condition.

b.

This license condition shall be effective for three years from the date of issuance of Amendment No.150.

D.

This license if effective as of the date of issuance and shall expire at midnight, June 29, 2007.

FOR THE ATOMIC ENERGY COMMISSION A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Original Signed by A. Giambusso

Enclosure:

Appendices A and B - Technical Specifications Date of Issuance:

December 27, 1974 1

Amendment No. 28, 30, 46, 55, 113, 150, l

Docket No. 50-213 B14426 l

P I

Haddam Neck Plant Proposed Revision to Technical Specifications (Marked-up Copy)

May 1993

t

. 3 April 4, 1991 I

to the Act and 10 CFR Parts 30, 40, and

~

(3) CYAPCO, pursuant 70, to receive, possess, and use at any tipe any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources or reactor instrumentation and radiation monitoring equipment calibra-tion, and as fission detectors in amounts as required; (4)

CYAPCO, pursuant to the Act and 10 CPR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material, without.

restriction to chemical or physical form, for sample analysis or instrument calibration or associated with i

radioactive apparatus or components; and (5) CYAPCO, pursuant to the Act and.10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear material as may be produced by the operations of the facility.

C.

This license shall be deened to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

6 (1) Maximum Power level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1825 megawatts (thermal).

t (2) Technical Steei fications The Technical Specifications contained in Appendix A, as revised through Arendrent No. 135, are hereby incorporated l

in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

[(3)

Deleted per Ardt. 29, 10-24 76.]

1 (4) Fire Protection m

L icensee may proceed with and is required to corp 1 -

i.

((95tUll~,hk,,

the moe cations identified in Paragraphs 3.1.1

• sugh 3.1.19 of to "RC's Fire Portection Safety E-aation (SE) dated October 3,

.R on the facility.

. se modifications 6 return'*

-o power operation i

will be completed prio.

following the 1980 refuelin.

age.

In addition, the 34

.isee shall submi

. additional information 4'

..ified in Table 3.2 of this in i

accordar-ith the schedule contained therein.

the ev these dates for submittal cannot be met, the 11 ee CSF21X.C14 I

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I l

y 4

February 26, 1992 s %aa report, explaining the circumstances, together revised sched The licensee is required o imphaen trative controls identified in.5 of the SE.

The adminis r

+ ols sh_alLbedfrl!Tfect by December 31, 1978.

(5) Physical Protection The licensee shall fully implement and saintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10CFR73.55 (51FR27817 and 27822) and to the authority of 10CFR50.90 and 10CFR50.54(p). The plans, which contain Safeguards Information protected under 10CFR73.21, are entitled:

"Haddam Neck Plant Physical Security Plan,'

with revisions submitted through January 24, 1989; "Haddam Neck Plant Guard Training and Qualification Plan," with revisions submitted through January 27, 1983; and 'Haddam Neck Plant Safeguards Contingency Plan,' with revisions submitted through January 27, 1983; and "Haddam Neck Plant Safeguards Contingency Plan," with revisions submitted through December 9, 1983. Changes made in accordance with 10CFR73.55 shall be implemented in accordance with the schedule set forth therein.

(6) Intearated lmolementation Schedule The Connecticut Yankee Atomic Power Company shall implement and a.

maintain in effect the Integrated Implementation Schedule Program Plan (the Program Plan) to be followed for scheduling of plant modifications and engineering studies.

The Program Plan shall be followed from and after the effective date of this license condition.

b.

This license condition shall be effective for three years from the date of issuance of Amendment No. 150.

D.

This license is effective as of the date of issuance and shall expire at midnight, June 29, 2007.

FOR THE ATOMIC ENERGY COMMISSION A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Original Signed by A. Giambusso

Enclosure:

Appendices A and B - Technical Specifications Date of Issuance: December 27, 1974 Amendment No. 28, 30, 46, 55, 113, 150

~

APR 2 61990 INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEllLANCE REOUTREMENTS SECTION ffAGE

' TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0lNTS.......................

3/4 3-19

~ TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS............

3/4 3-21 3/4.3.3 MONITORING INSTRUMENTATION..............................

3/4 3-23 TABLE 3.3-4 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS...........................................

3/4 3-24 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS................

3/4 3-25 Movabl e Incore Detectors.............................3/4 3-26 Seismic Instrumentation..............................

3/4 3-27 TABLE 3.3-S SEISMIC HONITORING INSTRUMENTATION...................

3/4 3-28 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................

3/4 3-29 Meteorlogi cal Instrument ation........................

3/4 3-30 TABLE 3.3-6 METEORLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-31 TABLE 4.3-5 METEORLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................

3/4 3-32 Accident Monitoring Instrumentation..................

3/4 3-33 TABLE 3.3-7 ACCIDENT MONITORING INSTRUMENTATION..................

3/4 3-34 TABLE 4.3-6 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................

3/4 3-38 m.

m.,_m_

TABLE 3. 3 8 p!EE CE'ECT!O!! EYETEMS...............................

4, mz DELerg

, Radioactive Liquid Effluent Monitoring c/> Instrumentation......................................

3/4 3-44 TABLE 3.3-9 RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION......................................

3[43-45 TABLE 4.3-7 RADIOACTIVE LIQUID EFFLUENT fl0NITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............

3/4 3-47 Radioactive Gaseous Effluent Monitoring Instrumentation......................................

3/4 3-49 HADDAM NECK VI O'/

Amendment No. 125

May 8 1992 0

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS

[

PAGE SECTION TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM..........................

3/4 7-6 Main Steam Line Trip Va1ves.............................

3/4 7-7 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.........

3/4 7-8 3/4.7.3 SERVICE WATER SYSTEM....................................

3/4 7-9 3/4.7.4 SNUBBERS................................................

3/4 7-10 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL...................

3/4 7-10a 3/4.7.5 SEALED SOURCE CONTAMINATION.............................

3/4 7-14 3/4.7.5 -f!RE SUPPRESSION SYSTD'.S Fira w ter Supply / Distribution System 3/4 LIS a

3/4 7-19 Spray and/nr Sprinkler.-.Systeme p

K C0 Systame._______.....................................

3/4 7-21 3

3/4 7-22 Halnn Kysteme.

3/' 7-23 Fire Hose Stetions-TABLE 3.7-4 -F4 RE-HOSE-STAT 40NS...................................

3/4 7-24 Yard rire Hydrants and Associated-Hydrant-Hese-Houses...

3/4 7-25 TABLE 3.7-5 -YARD-F4 R E-HYGRANT S...................................

3/4 7-27 4.7.7

.FIRF RATEn As$EMBl_fES...................................

3/4 7-28 3/4.7. 87 FLAMMABLE-14@105-GONTROL...............................

3/4 7-30 3/4.7.9 FEEDWATER ISOLATION VALVES..............................

3/4 7-33 TABLE 3.7-6 FEEDWATER ISOLATION VALVES...........................

3/4 7-32 3/4.7.10 EXTERNAL FLOOD PROTECTION...............................

3/4 7-33 3/4.7.11 PRIMARY AUXILIARY BUILDING AIR CLEANUP SYSTEM...........

3/4 7-34 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating...............................................

3/4 8-I TABLE 4.8-1 DI ESEL GENERATOR TEST SCHEDULE.......................

3/4 8 6 Shutdown................................................

3/4 8-7 3/4.8.2 D.C. SOURCES 0perating...............................................

3/4 8-8 TABLE 4.8-2 BATTERY SURVEILLANCE REQUIREMENTS....................

3/4 8-10 l

Shutdown................................................

3/4 8-11 m i HADDAM NECK i

X Amendment No. JU,151 v

con

-t APR 2 619S0 E fl i

BASES t

SECTION E9.1 l

s r3/4.4.7 CHEMISTRY..............................................

.B 3/4 4-7 3/4.4.8 SPECIFIC ACTIVITY......................................

B 3/4 4-7 3/4.4.9 PRESSURE / TEMPERATURE LIMITS............................-

B 3/4 4.B 3/4.4.10 STRUCTURAL INTEGRITY...................................

B 3/4 4-12 i

3/4.4.11 REACTOR COOLANT SYSTEM VENTS...........................

B 3/4 4-12 3/4.5 EMERGENCY CORE COOLING SYSI{!g 3/4.5.1 & 3/4.5.2 ECCS SUBSYSTEMS................................

B 3/4 5-1 3/4.5.3 REFUELING WATER STORAGE TANK...........................

B 3/4 5-2 3/4.5.4 pH CONTROL SYSTEM......................................

B 3/4 5-2 i

i 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.....................................

B 3/4 6 '

3/4.6.2 CONTAINMENT AIR RECIRCULATION SYSTEM....................

B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES............................

B 3/4 6-3 I

3 /4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...........................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.........

B 3/4 7-2 3/4.7.3 SERVICE WATER SYSTEM....................................

B 3/4 7-2 3/4.7.4 SNUBBERS................................................

B 3/4 7-3 3/4.7.5 SEALED SOURCE CONTAMINATION.............................

B 3/4 7,

3/4.7.64 114tE-9BPPRE1916N 0 7:!CT.0................................

/

7' f

3/4.7.7 a F M TED A33Easui3...................................

;/ 7

3/4.7.B GT."0LE L'^J:00 C0%T^^L...............................

': :/ 7:

3/4.7.9 FEEDWATER ISOLATION VALVES..............................-

B 3/4 7-6 3/4.7.11 EXTERNAL FLOOD PROTECTION...............................

B 3/4 7-6 3/4.7.1 PRIMARY AUXI LI ARY BUI LDING AI R CLEANUP SYST EM...........

B 3/4 7-6

' bE LET E D

_=

cetR t

HADDAM NECK XIV Amendment No. 125 ww7

6/16/92

~

INSTRUMENTATION gggggggyg4

~

f

-FIRE-DETEfT4GHNSTMMEMT*TIGN l

' i.iHITiHG CONDITION FOR OPERATION-

%+1

[ G re --

a_ch 3.3.3.6 </ As a minimuc, the f4re detection tutrumentation for detection zone shown in Table 3.3-8 shall be OPERABLE.

Whenever

systems, structures, components, r

equipment N

APPLICABillTY:

be OPERABLE.

protected by the fire detection instrumentation are required t ACTION: \\

but no less than the minimum re ired fire detection a.

Wi

any, instruments shown in Table 3.3-8 inoperable, restore the inoperable instrument (s) to OPERABLE stptus within 14 days or within thh next I hour establish a firp' watch patrol to inspect the zone (s\\)with the inoperable instrpment(s) at least once per is lopated inside the containment, hour, unless 'the instrument (s) then inspect th'ht containment zone At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (or monitor the conthinment air temp fature at least once per hour per Specification 4.

1.5).

b.

With less than the minun.um r uired fire detection instruments in any fire zone shown in le 3.3-8 operable, within I hour establish a continuous fir atch to inspect the zone (s) with the inoperable instrument (s),

unless the instrument (s) is located inside the containment then \\(nspect that containment zone at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (or monitor the containment air temperature s

at least once per hou per Specifica ion 4.6.1.5).

The provisions of 'pecification 3.0.3 at not applicable.

c.

\\

SURVElltANCE REOUIREMENTS x

/

4.3.3.6.1 Each of he above required fire detection i uments which are accessible during, lant operation shall be demonstrated OPERABLE at least of a TRIP ACTUATING DEVICE OPERATIONAL once per 6 mont,hs by performanceFire detectors which are not accessible during TEST.

be demonstratgli OPERABLE by the performance of a TRIP ACTUATING DEVICE TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> \\unless OPERATIONAL Detectors which cannot be reset are not performedjn/the previous 6 months.

be demonstrated OPERABLE by performance of a TRIP ACTUATJNG required to

\\

DEVICE ERATIONAL TEST.

HADDAM NECK 3/4 3-40 Amendment No. U E,153 CD22,

Y

)

APR 2 61990 i

SURVEllLANCE RE

ENTS i

x s

4.3.3.6.2 Supervised c t

detector alarms of each

.,of the above required fire detectio nts shall be demonstrated -

OPEPABLE at least once per 6 mo 4.3.3.6.3 Nonsuperv circuits, associated with detec larus, between

'the instrument a e control room shall be demonstrated OPE t least once per 31 3

P T

gis A6E uTE4Tso Y

LAuk p

f f

e%

,O f;

D v

HADDAM NECK 3/4 3-41 Amendment Nn, 1M

TABLE 3.3-8 Minimum Number

-Minimum' Numb l

Smoke Detectors Heat Detect s i

NLcation' OPERABLE / Detectors OPERABLE /D ectors

.i Available -

Avail le

]

1.

Containment (R-3)

-19/22*

24/32 i

(Ina essible)

!l 2.

Cab SpreadingArea(S-3A) 21/28*

l 3.

IA Die 1 Generator Room (0-1) 6/7 4.

IB Diesel enerator Room (D-2) 6/7 5.

Switchgear m(S-2) 35/35 j

1 6.

Containment Ca e Vault (R-1) 8/8 YHlh A66 l

7.

Waste Disposal B1

.(W-1) 3/4 8.

Auxiliary feedwater

,p Room (R-2) 2 L ygwTl coat.d I

i 9.

Primary Auxiliary Bldg.. A-1) 42/43

.i g g

(excluding RHR Cubicles, Zones A-1E, A-IF)

RHR Cubicles (A-1E, A-IF) 1/1

[

g j

~

10. Control Room (S-1A, Not includi 13/18*

kitchen)-

11. Screen Well Bldg.

j' Pump Motor Room (P-1 P-1B) 8/9***

Hypoclorite Storage.oom (P-IC) 1/1 i

12. Spent Fuel Bldg.

'l Storage and Dec. Area (F-1A) 11 l

Spent Fuel Po (F-1B)

• 4/5

13. PAB Charcoal Fil r Bank Heat ~ Detector 7/7 (A-1N) (o' et detectors only) 4/4

14. High pressur turbine deluge (T-IF) 1

15. Hydrogen al oil reservoir deluge (T-10) a

16. Turbi lube oil reservoir (T-1B) 11/1 i

i

• No o adjacent detectors shall be inoperable at the same time.

l

• • M'.imum of 6 heat detectors per reactor coolant pump must be OPEPABLE.

ne detector inoperable cannot be one of the three existing detectors n

.e upper level of the Screen Well. Building.

HADDAM NECK g/

3/4 3-42 Amendment No. J21I, 126

M

APR 2 61930

" 33;8 fpo,Jd ~,g u

m 1

1 Minimum Number Minimum Numbe Smoke Detectors Heat Det s

OPERABLE / Detectors OPE

/ Detectors ocation Available Available 4/4

~17.

Turbine buil zzanine under generator (T-IF) 6/6

18. Turbine building cranewell (T-IC)

19. Switchgear Room (New Switchg utiding) 3

20. Baj Room Aew Switchgear Building) 2/2

-f 55 A6E Ime.6xtocAcov bdc oscp N-

-/-

J e

e%

e

[jQ(

HADDAM NECK 3/4 3-43 Amendment No. 125

~

APR 2 61990 PLANT SYSTEMS

]f g

b "E 00^^^:: = G /370;3 2/(26 r;": tlATG" ;U";"J/0!W"I^ " ^" C'l:T:"

2 iTING CONDITION FOR OPERATION

.-3.7.6.

The Fire Water Supply / Distribution System shall be OPERAB with:

a.

A least two high pressure fire suppression pumps, ea with a capacity of 2500 gpm (at Rated Pressure), automatic. art capabh ty with their discharge aligned to the fir suppression

header, d

b.

An OPERABLE ow path capable of taking suct from the Connecticut Ri'vtr and transferring the wat through distribution piping with OPERABj.E sectionalizing contr valves and the first valve ahead of the%ter flow alarm dev e on each sprinkler, hose standpipe or Spray Sistem riser requi d to be OPERABLE per Specifications 3.7.6.2,

.7.6.5, an /3.7.6.6.

APPLICABILITY: At all times.

ACTION:

a.

With one pump inoperable, estore th inoperable pump to OPERABLE status within 7 days or rovide an alt ate method of supplying fire water.

b.

With the Fire Wat.

Supply / Distribution Syste otherwise inoperable, establish an hourly Fire Watch Patr for the affected areas, and provide a backup Fire Water Supply / Dis ibution System within 24 hods or the plant shall be placed in at st Hot Standby wit 61n the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shut n within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

The ovisions of Specification 3.0.3 are not applicable.

e

~ - c-HADDAM NECK 3/4 7-16 Amendment No. 125 i

APR 2 61990 LANT SYSTEMS S VEILLANCE REOUIREMENTS

/

4.7.6.1.

The Fire Water Supply / Distribution System shall be demonstra d OPERABLE

)

a.

At least once per 31 days on a STAGGERED TEST BASIS by st ing l

eac pump and operating it with flow. The diesel pump s 11 run j

f for 3 minutes and the electric pump for 5 minutes.

b.

At least nee per 31 days by verifying that each. val (manual, power-ope ted or automatic) in the flow path that s not locked, sealed, or herwise secured is in its correct po tion, j

c.

At least once r 12 months by cycling each te able valve in the flow path throu at least one complete cycl of full travel, P

d.

At least once per 1 months by perfoming system functional test which includes simul ed automatic actua on of the system l

throughout its operati sequence, and j

1)

Verifying that each develo at least 2500 gpm at a system head of greater han or equal to 100 psig at Rated t

Speed, 2)

Cycling each valve in the ow path that is not testable during plant operation ou at least one complete cycle of i

full travel, and j

1 3)

Verifying that each igh pressure ump starts automatically g

and sequentially t maintain the'F e Water Supply /

Distribution Sys m pressure greater han or equal to j

75 psig.

e.

At least once per years by perfoming a flo test of the j

Distribution System in accordance with Chapter Section 11 of j

the Fire Prote ion Handbook, 14th Edition, publ ed by National Fire Protect n Association.

4.7.6.1.2 The fir ump diesel engine shall be demonstrated 0 RABLE:

l l

a.

At leas once per 31 days by verifying:

i 1) he fuel storage tank contains at least 130_ gallons of el, and The diesel starts from ambient conditions and operates foF i

least 30 minutes with flow.

i N S 9 ARC l WTEAYLoQALLX btJk 1

Jg$

Onfq HADDAM NECK-3/4 7-17 Amendment No. 125

t APR 2 61990 3

V LANT SYSTEMS S

ElttANCE REOUIREMENTS (CONTINUED)

't At least once per 92 days by verifying that a sample of d'ies I

b.

.uel from the fuel storage tank, obtained in accordance wit ASTM-l D2J0-1975, is within the acceptable limits specified in T e I of

.i

/

AS D975-1977 when checked for viscosity, water and se nt.

c.

At lea once per 18 months, during shutdowny by/

l J[

Spbj ting the diesel to an inspection isp ac rdpnce with proced'esiprephredinconjhnctionwithit

'andfact,urebfs'

/

i tions for the class of. service' nd

, - : r-81 r:econnen i

27 ferifying t diesel starts from ambi conditions on the auto-start si al and operates for g, ater than or equal to

-f 30 minutes whil loaded with the f e pump.

f 4.7.6.1.3 The fire pump diesel arting 24-v t battery bank and. charger shall be demonstrated OPERABLE:

i a.

At least once per 7 days by

' ying that:

l 1)

The electrolyte level en battery is above the plates, and

.j i

2)

The individual ov all battery v tage is greater than or f

equal to 24 volt.

b.

At least once p r days by verifying that "he specific gravity is appropriate continued service of the l ttery, and c.

At least once er 18 months by verifying that:

l

/

1)

The be teries, cell plates _ and battery racks s w no visual indication of physical damage or abnormal deteri ation, and i

/

2) e battery-to-battery and terminal connections-are lean, tight, free of corrosion and coated with anticorrosio l

material.

l l

(TRt5 9A6s lOW.Wto4 ALLY 3L.Ad4 m

s ONh HADDAM NECX 3/4 7-18 Amendment No. 125 t

i*

M la ACC (MTEcytog AQ,,

gg

' PLANT SYSTEMS

-+

-WUci A;G/07. ;^CMXtr MSTm; cd=tl-L4 x!?!NC C f.p!'I E C" 0" m ! O" 7

DELETED) c.dct

..: m w ng !;r:; nff:: !;r'dkr 53;;n; ;5:12 i: 0"r".'."'I:

3.7.6.2 Sprinkler Systems

~

1)

Maintenance shop

)

Turbine building, El. 21'6",

Turbine building mezzanine,

)

Turbine building beneath the turbine floor and un r the high 4) pressure turbine, urbine building between column lines C and D d column 5) n mbers B and 12 under the Sg' 6" elevation

• 6)

Lube Oil Storage room, 7)

Cabl Spreading area,*

8)

Prim Auxiliary building,*

9)

Servic Building,

10) Chemist, Lab,

11) Nachine ShQp, 12)

Intake Strdtture (diesel fuel storag room)

13) Diesel Fire mp,

14) Service Water umps Water Curtain

15) Cable Spreading allway Water Cu ain,*

16) East Cable Shaft

'B' Switchge / Building), and

17) West Cable Shaft

• Switchg r Building) b.

Deluge Spray Systems 1)

High pressure turbine, anual),

(manual, and Welt (au)omatic).

2)

Hydrogen seal oil unit t

3)

Turbine Building Cran c.

Preaction Systems 1)

Turbine building mezzanine under enerator, 2)

Diesel Generator Room A, and 3)

DieselGeneraferRoomB.

4)

Turbine lube / oil reservoir APPLICABILITY: Whenever stems, structures, component or equipment ed to be OPERABLE.

protected by the spray nd/or sprinkler systems are requ ACTION:

rinkler With one or more of the above required Spray and/or s fire a.

Systerf inoperable, within I hour establish a continu reas in watet/with backup fire suppression equipmer'. for those which redundant systems or components coulc be damaged o present xposure fire hazard to other components (these areat tch e

anterisked (*)); for other areas, establish an hourly fire atrol.

The provisions of Specification 3.0.3 are not applicable.

b.

Areas where redundant systems or components could be damaged.

HADDAR NECK 3/4 7-19 /

AnendmentNo.17(,147 coes j/L f 1

APR 2 61990 j

4 I

ktANT SYSTEMS S

ILLANCE REQUIREMENTS j

i x

4.7.6 Cach of the above required Spray and/or Sprinkler System shall be demonstraf o OPERABLE:

i e

a.

At east once per 31 days by verifying that each va e (manual, i

powe operated, or automatic) in the flow path, t t is not -

locke sealed or otherwise secured in position is in its correct-positio b.

At least.on per 12 months by cycling eat testable valve in the flow path th ugh at least one complete ele of full travel, c.

At least once pe 18 months:

1 1)

By performing system func nal test which includes i

simulated automa ic actuat n of the system, and:

[

a)

Verifying that

hp' system alarm check / main actuation t

valves in the f aw path actuate to their correct positions on 4 si' lated test signal, and l

/

j b)

Cycling en valve in the flow path that is not testable -

I during lint operation hrough at least one complete cyc1 full travel.

2)

By visual inspection of the spra headers to verify their-i integr ty, and j

3)

By isual inspection of etch nozzle t verify that there is

[

nd blockage and that each spray area is et obstructed.

j d.

At ast once per 3 years by performing an air ow test through ch open head system and verifying the supply pi ng and nozzles t

are unobstructed.

Ij 5

I i

H Rti A66 MTEuTtOO ALAN ELA>0k L

l t,a 1

j l

t i

I i

HADDAM NECK 3/4 7-20 Amendment No. 125

t 7'

PtANT SYSTEMS l

... ~ - - -... -

ww er 4 er s u 4.7 i

^

U"IT;;;; 00';31T;0" TOR 0*=T 0 ?

tiLET'Eh cdd-

^

{.7.6.3 wi!%. ';;h P=n= T Sy;tn. hil k OICICLE -M. U ^

=ht.;. nakraf-stecoge4et4h:1 6.;. d n h b c' ;; :. n t n i s h i ; f..e t i.7 i

th 90% charge weight:

a Cable Vault - 44 bottles, and b.

rimary Auxiliary Building Charcoal Filters - 8 bottles.

l APPLICABILIT

(

Whenever systems, structures, components, or equipment pro cted by.the High Pressure CO Syste are required to be OPERABLE.

l 2

ACTION:

a.

With one or mo of the above required igh Pressure C0 Systems inoperable, with I hour establish a ontinuous fire w!tch with i

backup fire suppr sion equipment f the unprotected equipment i

and/or area.

i b.

The provisions of Spect ation

. 3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.7.6.3 Each of the above re ired Hi Pressure CO Systems shall be demonstrated OPERABLE:

2 a.

At least once per months by verify C0 of full charge weight, an$ storage bottle weight to be at least 9 b.

At least once er 18 months by:

l 1)

Verif ng that a111 system components op ate properly when i

can 1 devices are manually operated and utomatic devices ar actuated by a simulated signal, and 2)

Performance of an air flow test through syste. headers and i

nozzles to assure no blockage.

i 4

J.-

pm s.

(

TH0 %CE l"Tt""d^"'T g#tc, l

\\

~

HADDAM NECK 3/4 7-21 /

Amendment No.M 126 f) / Lt ')

~

i

%pp...

d I 'THIS AGE lNTEWOMAtM/

1 PLANT SYSTEMS N.__ __.~ ~ ~ ~'

, s cL

..n;:, ;,;;m; la P

d'"IT:"' ;;;;T;;s; i;R 6;ie uyn 3.7.6.4ATh:en=p;::1,..001.....k. af-sterege-een

.... _ ' 7.'. : f

@E.LET6 cel

, r,

~

0, am..Lii 6 s,TETJuE

U. yJ.

s than 95% and a pressure of not less than 324 psig:

in k m.

l'

'A' Switchgear Room - 8 containers, b.

Control Room - 3 containers.

c.

• B Switchgear Room - 2 containers d.

"B" Bat ry Room - I container APPLICABILTTY: Whenev t

systems, structures, compo nts, or equipment E.

protected by the Halon3ystem are required to be OPE ACTIOS:

equired Halon 1301 Systems a.

With one or more f the above a continuous fire watch with inoperable, within I ur establis for the unprotected equipment backup fire suppression equipme and/or area.

3.0.3 are not applicable.

b.

The provisions of Specificati SURVEILLANCE RE001REMENTS s

4.7.6.4 Each of the abo required Hal 1301 Systems shall be demonstrated OPERABLE:

At least once er 6 months by verify 1 each Halon storage container net peight to be at least 95% of fb 1 charge weight an a.

with a pressure

.of. not less than 324 p ig (adjusted for l

temperature, and b.

At least nee per 18 months by:

rly when erifying that all system components operate pro manual devices are manually operated and automatic devices 1) are actuated by a simulated signal, and Performance of an air flow test through headers and nozz s

2) to assure no blockage.

l AmendmentNo./f5,147 3/4 7-22 HADDAM NECK

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I Tuts 9^cc teco^"-7 PLANT SYSTEMS i

- ::===:=

i i:":T:= _00" :HcN40R, = T:=

@cL*T6 at

' '9' - ? ? ' 9 " 5 ^"S" *.*'l.

n = '+ *'--

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ha 3.7.6.5 MPPLICABILITY: Whenever systems, structures, components, or equipme as protected by the fire stations are required to be OPERABLE.

I l

a ACTI

)

ith one or more of the fire stations listed in Ta e 3.7-4 a.

operable.

l ity, or ithin one hour provide a hose of equivalent cap 1) blish a continuous fire watch for e area of the ed fire station if the inoperable h e provides primary l

l 2)

Es i

suppre ion capability and provide _ a ese of equivalent affe l

n capacit ithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or s

el if the affected hose 3)

Establish a hourly fire watch pa ity and provide a hose of suppression capab l

provides bat s.

l equivalent capa ity within 24 ho l

cation 3.

3 are not applicable.

b.

The provisions of Speci SURVEILLANCE REOUIREMENTS X/

Table 3.7-4 shall be demonstrated I

I 4.7.6.5 Each of the fire stations sven i

OPERABLE:

a.

At least once per I days by vi al inspection of the fire i

stations to assure 1 required equipme is at the station, i

.)

b.

At least once p 12 months, by:

the hose for inspection, onducting a

hose atic test at a pressure of at 1 st 50 psig above-j i)

Removi hydroum system pressure and re-racking', and max i

d gaskets Jn specting all gaskets and replacing sny degra 2) he couplings.

alve to i

least once per 3 years, by opening each fire station verify valve OPERABILITY and no flow blockage.

f c.

I 3/4 7-23 /

AmendmentNo.//I,147 HADDAM NECK p/ y c

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coes

TABLE 3.7-4 EWOh

,,,,.,, ~, -

_ m. m m

\\lRESTATION ELFVATION PROTECTED AREA DESIGNATION AND LOCATION 21'6 Diesel general Rooms-Lock /

FHC. 3 Corridor outside H.P.

Shower Area & H. P. Supp t Offices Area.

FHC.- 4, rvice Bldg Hallway 21'6" Cable Spreading Area-tetry Auxiliary Building - able outh Vault FHC - 5, CorTr der outside CAS Sg'6" Corridor to CAS FHC - 6. Servic idg, Hallway 21'6' Cable Spreading rea-Primary Auxiliary But ing FHC - 7, Primary A iliary Building 21'6" Primary Auxi ary Building

- North 35'6" Primary Aux liary Building FHC - 8, Primary Aux 1Jiary Building 21'6" Service ter Pumps FHC - 9 Screenwell B0 ding FHC - 10, "A" Switchge Room 41'6" "A" Swi hgear Room 21'6" Air C. pressors FHR - 1, Turbine Buildin North Col. C-Il 21'6" 01 torage Room FHR - 2, Turbine Building, Drth Col. X-12 nder Main Turbine Generator 21'6' FHR - 3, hrbine Building, East Col. 0-4 21'6" Feed Pu=ps FHR - 4, Turbine Building, East Col. C-7 Under Main Turbine Generator 21' FHR - 5. Turbine Building, South Col. C-1

'6" Under Main Turbine Generator FHR - 6, Turbine Building, South Col. W-1 21' "

Lube Oil Reservoir FHR - 7, Turbine Building, West Col. B-9 21'6' H Seal Oil Unit FHR - 8, Turbine Building, 2

West Col. B-4 37'6" eedwater Control FHR - 9, Turbine Building, East Col. C-3 37'6" Fee water Heater il FHR - 10, Turbine Building East Col. C-7 ~

37'6" "A" Sw chgear Room

, FHR - II, Turbine Buildi East Col. C-19

~

FHR - 12, Turbine But

ing, 37'6" H Yap r tractors 2

WestsCol.

4 59'6" High Pressur Turbine FHR - 13, Turbine 11 ding, North

. I-12 59'6" Control Room eM FHR - 14, Turbi

Building, Eas Col. C-10 FHR - 15. Tu ine Build'ng, 59'6" Lew Pressure Turbi s

st Col. C-E yggg pA6E l NTE9 Tic AU T tes:

re M

ggg h7

,H FH - Fire Hose Cabinet pS-FireHoseStation 3/47-24[

Amendment No. #5',147 HADDAM NECK caos q / L / L,,

/

/

I.L :.M

-f4*HMMS-FHR - 16 Turbine Building, 59'6" Generator / Exciter East Col. C-2 i

FH

' 7, Turbine Building, 59'6" Generator / Exciter South Col. V-1 FHR - 1 ATurbine Building, 59'6" Low Pressure Tu nes Best Col. B-4 FHR - 19, Turbine Building, 59'6" High Pressu Turbine ' -

West Col. B-9 1

FHR - 21, Maint. RCA Shop, South 21'6" Electri ables FHR - 22, Maint. %.ob 21',6*

Elect c Cables SouthCol.FY l

FHR - 23, Maint. Shop, 21'6

• ctric Cables l

North Col. D-4 FHR - 24, Spent Fuel Building, st 21'6' Fuel Storage Building FHS - 5,

• B' Switchgear Building',

13'6" Production Test Shop

' North FHS - 6, "B" Switchgear Building, 6"

Maintenance Electrical Shop North FHS - 7,

• B" Switchgear Building, 41'

'B' Switchgear/ Battery' - Rooms North FH-1 Turbine Building at FHR-13 59'6*

ontrol Room i'

HR-Il 37'6" "A'sSwitchgear Room TurbineBuildingat)ildingat21'6' FH-2 Prim Auxiliary Building Primary Auxiliary u FH-3' FHC-7 FH-4 Primary Auxil y Building at 35'6" Primary iliary Building FHC-8 FH-5 Service B ding at FHC-4 at 21'6' Cable Vault Notes.

FHR = Fir,e ose Reel f

FH = Fijt Hose i

FHC -f ire Hose Cabinet FHS4 Fire Hose Station 5

i M

E W E k71~t O @ Q,Y b g 5

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HADDAM NECK th-/Y 6 3/47-24a!

Amendment No. JJJ.147

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PLANT SYSTEMS.

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" P m g_11yeasuT aua,_msget"Tr 7= ;;= ;;nn i

~

G G LIC O':'0 0-C = =

& LLETEU ed 3.7.6.6 ^7se yard 44r-hW-" - d ""~' ** *d #8 -^

'a - " "-- C'"-

j Td' *.? I :h11 h 0% 1 1 f

hPLICABIt1TY: Whenever systems, structures, components, or equipment in ih '

s protected by the Yard Fire Hydrants are required to be OPERABLE.

ar ACTIO :

tre hose

[

ith one or more of the yard fire hydrants (and associate a.

uses) given in Table 3.7-5 inoperable,.

ithin one hour connect sufficient additional le ths of 1) inch diameter hose on an OPERABLE hydrant to rovide seYyice to the unprotected area (s) if the ino rable hydrant or hose house is the primary means of fire ppression for any' l

i safety-related areas, or the safety-related' l

2)

Establishgan hourly fire watch patrol i rant or fire hose house area (s) prb{ected by the inoperable hif fire detection is available l

1 provide the a itional hose within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or Establish a cont wuous fire wat in the safety-related 3) area (s) protected by the inope abla hydrant or fire hose house i

if fire detection is et avaMable in the area and provide the j

additional hose within 4

'urs, or b

4)

Provide additional hose hin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the inoperable-l i

hydrant or fire hose use the backup means of fire suppression for any fety-r atedarea(s).

l b.

The provisions of Spec ication 3.0.

re not applicable.

[

SURVElllANCE REQUIREMENTS x

I 4.7.6.6 Each of the ya fire hydrants and associate tre hose houses given t

in Table 3.7-5 shall emonstrated OPERABLE-i ce per 31 days by visual inspection of.

e fire hose house l

At least and that the a.

to assure'all required equipment is'at the hose hous hydran is accessible and unobstructed, ast once per 6 months (once during March, April or

^ and during September, October or November), visually insp ting l

b.

At s-

l onetch yard fire hydrant and verifying that the bydrant barrel j

?-

ry and that the hydrant is not dar. aged, and 1

e _

THd iAGE ktJTEhynOOALO(. MLANK i

--m I

(cald 3/4 7-25 /

Amendment No. 175,147 HADDAM NECKgJ / Y,4 am 1

,,SUkVEllt ANCE REOUIREMENTS (Continued)

['

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X c.

ast once per 12_sonths,~by:

1)

Condu a hose hydrostatic test (of t ose in the hydrant _ho ouse) at a pressure at st 50 psig above the maximum system

sure, I

2)

Inspecting all the gaske nd replacing any degraded gaskets l

in the couplings, an 3)

Opening each ve and flushing each t to verify valvi OPERABIL and no blockage.

h

~

"T ats 9A66 INWlOUAU Lo Y r

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l HADDAM NECK 3/4 7-26 Amendment No. 125 h / }$f _

i TABLE 3.7-5 3E.LETED r ===m:

op FIRE HYDRANT R

g Fire hyd south of screen house *

1. 1 FP-64 l

Fire hydrant so of turbine building FP-V-165 l

1. 3 FP-V-208 Fire hydrant by fuel rage tank

• 5 Fire hydrant south of radwas stora utiding

1. 4 FP-V-206 i

wa storage tank

• f5 FP-V-205 l

Fire hydrant by recycle prima 1

Fire hydrant by north tank fara*

1. 6 FP-V-201 Fire hydrant h of "B" switchgear building

1. 7 FP-V-200.

i i

FP-V-196 Fire ant north of screen house

1. 9 FP-425 ire hydrant north west of diesel building i

Tm 9nse turconocacey Bua,at h

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N,;;C N G hydi; Tit 0 I1/2--$. 00 AiC C IAAA A-AA*

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3/4 7-27 V Amendment No. ///.147 HADDAM NECK en m

V APR 2 61990

. PLANT SYSTE j

3/4.7.7 a RC A0""Z O LJ

-4 1 &fYW b V'1J l 1 2V' T VTT VI LT7i A Vil 3.7.

All fire rated assembites (walls, floor / ceiling, cable tray enclos res, and other fire barriers) separating safety-related fire areas or separat g portions of redundant systems required OPERABLE for safe shu own within a tre area and all sealing devices in fire rated assembly pghetratio (fire doors, fire dampers, cable, piping, and ventilati duc.t penetration eals) shall be OPERABLE.

APPLICABILITY:

At all times unless otherwise determined that t separation of sa ety-related fire arei.s or separating portions redundant systems important o safe shutdown within a fire area is not r quired based on the MODE of ope tion.

ACTION:

+

a.

With one or mo of the above required fire r ed assemblies and/or penetrat sealing devices inoperab, within I hour:

1.

Determine tha he fire areas / zones n both sides of the affected fire ed assembly and/o penetration sealing device are monith ed by either a OPERABLE fire detection or automatic suppres n system at he fire barrier and establish a fire wa h patrol at inspects both areas at l

least once per hour, r

watch on at least one side of the 2.

Establish a continuous

. ly and/or penetration seal.

affected fire rated asse b.

The provisions of Specific ion 0.3 are not applicable.

SURVE1LLANCE RE0VIREMENTS 4.7.7.1 At least once per 1 onths, the above r utred fire rated assemblies and penetration aling devices shall be erified OPERABLE by performing a visual inspec on of:

a.

The exposed s faces of each fire rated assem b.

At least 1 of the fire penetration pipe and ca e assembly penetrati s.

This 10% shall include proportional equal numbers of fire enetration pipe and cable assemblies conta ing each type of pene ration seal material.

If a type of penetrati n seal i

materfaldoesnotsatisfytestacceptancecriteria,an dditional

^

sample of such fire protection pipe and cable assembly-l

+

pen 6trations as was initially inspected shall be visually 1 spected. This examination process shall be continued un 'I a ample of the particular seal material type equal to the nu. er initially inspected satisfies testing acceptance criteria.

Samples shall be selected such that all fire penetration pipe d

1 cable assembly penetrations will be inspected every 15 ears.

l Rts 9AE - I uTEvTto.J A L.tX Du. Mc HADDAM NECK 3/4 7-28 /

c0C0 Amendment No. 125-lWb i

~ APR 2 61990 I

SYSTEMS

,/

SURV CE REOUIREMENTS (Continued) 4.7.7.2 At e per 18 months each fire damper sha e verified

~

OPERABLE by performing TRIP ACTUATING DEVICE OPERATIO TEST.

4.7.7.3 Each of the require re doors shall verified OPERABLE by inspectingtheautomatichold-(pen o

release closing mechanism and latches at least once per 6 months, b

erifying:

?

a.

That each locked closed e door closed at least once per 7 -

days, b.

That each un1 d fire door with electrical ervision is closed l

at least o per 7 days.

l c.

Tha ach unlocked fire door without electrical supervi is tised at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i i

f V

r Taa PAGE { OTEWttMALLY ELA*Jk-i

)

v i

5 5

j

.~

Amendment No. 125 HADDAM NECK 3/4 7-29

PLANT SYSTEMS APR 2 61990

]

g j

3/4.7.8f t^^;^^0 C L: C : % C : Z te:::= c=:::= r===:=

.1 3.7.8N Flamable liquids in volumes greater than 1 pint shall be restr ed l

from th) control room except under. the following conditions.

a.

W ten permission is obtained from the Supervising Co 1

)

s' Oper or or Shift Supervisor, b.

The flam ble liquid is contained in a suitabl container not to exceed one hart in volume, and j

~

\\

c.

A dedicated fire atch is assigned to t activity.

i APPLICABILITY: At all times.

{

l ACTION:

a.-

Upon determination that flamm e

uids in volumes greater than 1 pint are contained in the c rol room 9nd do not meet the conditions stated above, the flamma liquid shall e removed immediately from 1

the control room.

l b.

The provisions of ecification 3.0.3 are not a licable.

SURVElltANCE RE00 MENTS i

t 4.7.8 No l

/*-

A suitable container is non-spillable and has a flame arrestor in e

i nozzle.

i f cde' 6

E{

TE.kyT tO 4A LLY ItMC i

i

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I

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HADDAM NECK 3/4 7-30 Amendment No. 125 0l

APR 2 61990 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS hhe OPERABILITY of the Containment Atmosphere Gaseous R'adioactivity Mon'itor-ing System ensures that Gaseous Radioactivity Monitoring System will monitor inside containment as a means to detect RCS leakage.

3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the core. The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.

3/4.3.3.3 SEISMIC INSTRUMENTATION The CPERABILITY of the seismic instrumentation ensures that sufficient capability is available to determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capabili-ty is required to permit comparison of the measured response to that used in the design basis for the facility.

3/4.3.3.4 HETEOR0 LOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that suffi-cient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radio-active materials to the atmosphere. This capability is required to evaluate the need for initiatirg protective measures to protect the health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23, 'Onsite Meteorological Programs," February 1972.

3/4.3.3.5 ACCIDENT MONITORING INSTRUMENTATION The OPEPABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recomendations of Regulatory Guide 1.97, Revision 3

" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG-0737,

' Clarification of TMI Action Plan Requiremengovember 1980.

3/4.3.3.6 k HRE-CETCOHG" IZTE"OTIO"i %W oM The-OPERABR-I-TY-ef-4he-f6: det:c44en-4 estrum:ntetier en:gre: t6-t Stu adequate-warn 4ag.-capabH4ty-44-av404ble-.fw-. pen.pt-4etecti:n ;f fir::@-d that.IJra Suppression Sys.t.ams,-that are-actuated 4y-f.4r.e-4etect;r:, ci di5thlT9e ETtinguishing agent 3-"in a-timelymennir. Prcept d;tg;;j;n ;nd-suppre"%.of J.iras wi.D n$m the potentia! fer %g: :: :;f;;,, 7;;;;;g b

HannaM NrrK R1/4 3-7 i

Amendment No. 125

~

APR 2 61990 INSTRUMENTATION BASES

3. 4.3.3. 6[N E t,E"T e

Hesh I'5T"'"T"T'T!^' (Continued)-

j hruQment and is an integral element in the overall facility Fire Protect

Progr Fire detectors at are used to actuate Fire Suppression 5 s represent a more critically impor4 ant component of a plant's Fire

.ection Program than detectors that arl stalled solely for earl e warning and notifi-cation. Consequently, the sum number of LE fire detectors must be greater.

The loss of detection capabil or Fir pression Systems, actuated by fire detectors, represen significant degr ion of fire protection for any area. As a result, the establishment of a fi tch patrol must be initiated at artesflier stage than would be warranted the loss of i

detectors)haf provide only early fire warning. The establ ent of fre-quen1;Are patrols in the affected areas is required to provide ection capfbility until the inoperable instrumentation is restored to OPE TY.

3/4.3.3.7 RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION j

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

Alarr/ Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that i

the 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 I

requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

l 3/4.3.3.8 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION i

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous l

effluents during actual or potential releases of gaseous effluents. The Alarr/ Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the REMODCM to ensure i

that the alarm / trip will occur prior to exceeding the limits of i

10 CFR Part 20. The OPERABILITY and use of this instrumentation is consis-l tent with the requirements of General Design Criteria 60, 63, and 64 of l

Appendix A to 10 CFR Part 50.

3/4.3.3.9 BORON DILUTION ALARM i

The shutdown monitors provide indication of positive reactivity insertion during operation in Modes 3, 4, 5, and 6.

The indication is credited in the l

Boron Dilution design basis analysis.

l 3/4.3.4 FLOODING PROTECTION The liquid level instrumentation is provided to monitor liquid levels in areas of potential flooding caused by local pipe ruptures. The system ensures that early warning will occur so that protective action can be taken B3/4 3 3 [

Amendment No. 325 HADDAM NECK d/ 3

~

_ PLANT SYSTEMS BASES 3/4.7.4 SNUBBERS (Continued)

The service life is evaluated via manufacturer input an saintenance records (newly installed

snubber, seal

replaced, spring temperature area, location of in high radiation area, high The requirement to monitor the

replaced, potential fluid transient loading, etc.)

snubber service life is included to ensure that the snubbers periodically undergo a perfomance evaluation in view of age and operating conditions.

(Due to implementation of the snubber service life monitoring program after several years of plant operation, the historical records to da incomplete.)

for future consideration of snubber service life.

3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for plutonium. This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.

Sealed sources are classified into three groups according to their use, with Surveillance Requirements cor:nensurate with the probability of damage to a source in that group.

Those sources which are frequently handled are Sealed sources required "to be tested more often than those which are not.

sealed which are continuously enclosed within a shielded mechanism (i.e., devices)are sources within radiation monitoring or boron measuring considered to be stored and need not be tested unless they are removed from the shielded mechanism.

7-3/4.7.64f9E4MfiEEOT MM D3 0PEPABILITY of the Fire Suppression Systems ensures that adequate J

supp capability is available to confine and extin fires The, Fess 4cq equipment is occurring ihy.Jortion of the facility where safety-rey related areas do located and to enslrNay fires occurring outsi ession System consists of not affect safety related The Fire the Fire Water Supply /Distributi 41em Spray And/Or Sprinkler Systems, 00, Systems, Halon Systems, F tat'l and Yard Fire Hydrants and astociated Fire Hose House e to on Systems are adequate to minimize poten The Fire Suppr safety-yehted equipment and are a sa.jor element in the facili frettiction Program.

B3/4 7-4 /

AmendmentNo.fff,147 HADDAM NECK 0312 /

/

V

APR 2 61990 e

t

_ PLANT SYSTEMS BAsrs 3/4.7.gMM:ewrCD/ A 6

MPRC00:^^! OYC""C (Continued) 4 the event that portions of the Fire Suppression Systems are inoper fallernate' backup fire-fighting equipment is required to be made able in i

the affi o service, i

When the%reas until the inoperable equipment is restor inope e fire-fighting equipment is intend r use as a backup

'means of fire suppr n, a longer period of ti allowed to provide an' alternate means of fire ing than if th perable equipment is the primary means of fire suppress i

f

~

The Surveillance Requiremen rovide ass e that the minimum OPERABILITY requirements of the F uppression Systems ar In the eveg.Ahe Fire Suppression Water System becomes ino le, immediate l

corre3144ti measures must be taken since this system provides the r fire suppression capability of the plang 3/4.7.7IF3E MGE0450 '"" ::0--

Cb ge functional integrity of the fire rated assemblies and barrier penetqations ensures that fires will be confined (for a time of a ast equal tbQe minimum time rating of the associated fire barri from i

spreading to jacent portions of the facility. These de features minimize the po ility of a single fire rapidly inv ng several areas of the facility prior etection and extinguishin the fire. The fire barrier penetrations are assive element in facility Fire Protection Program and are subject to odic inspe ns.

l Fire barrier penetrations, includ ble penetration barriers, fire doors r

and dampers are considered f ional w the visually observed condition i

is the same as the as-des ed condition.

During periods of me when a barrier is not functio alternate measures are taken to vent the possible spread of fire. These sures' include verifyingAte operability of fire detection or suppression s ms on hp.th sidetAf the affected barrier and establishing-a fire watch patr or e

gost~ lng a continuous fire watch in the p ity of the affected barr l

3/4.7.8k> m. -

ec/

m mu c~

s.w, m l

TM mtreb.of n -91e ";: '- th: :=tml nr ;.hte..tiall.,. L a i

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. _-.. A4en-of* n.7,.... N.- 5555.' j 55Eb!5N!I).!' N S ' 555d!b f

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-l HADDAM NECK B3/4 7-5 /

Amendment No. 125

~

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~.

f

09/25/92 ADMINISTRATIVE CONTROLS An individual qualified in radiation protection procedures

• shall c.

be on site when fuel is in the reactor; d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent Q

responsibilities during this operation;

e. k LsiteJtra Br49ade-of-at-least-five-a,e;,bers* 1 hall be matntTined >

.nn site at_all timae.

TheJJre Brig:de sna14-not -include the

~

Shift _Superviter *ad two other-member-s-of-the-mhiettm-shift o u narettary_for safe chutdown-of the-p1 W :nd-any-personnel-required far__other essential functic sfring a fire-emergency; and f.

Administrative procedures shall be developed and implemented to limit the working hours of facility staff who perform safety-related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No. 82-12).

i The individual qualified in radiation protection procedures :nd firc-Srdgads-composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodats l

unexpected absence, provided immediate action is taken to fill the required positior'f".\\

l 8

[

i i

7 62 Amendment No. J2E,155 HADDAM NECK

} } (:>

ccie

no/25/92

• - ADMINISTRATI"I CONTROLS f.

Successful completion of the Thames Valley State Technical

~

" College associate's degree in Nuclear Engineering Technology program, provided that the individual was enrolled '.n the program by October 1, 1987.

2.

Dedicated STA: Must meet the STA training criteria of NUREG-0737, Item I.A.I.1, and have received specific training in plant design, and response and analysis of the plant for transients and accidents.

6.4 TRAINING

-4,4rl-A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Unit Director and l

shall meet or exceed the requirements and recomendations of Section 5.5 of ANSI N18.1-1971 and 10CFR55.59. The Director-Nuclear Training has the overall responsibility for the implementation of the Training Program.

6.4.2 A-training-program-for-the-Fire-Brigade-shah-be maintained trnder' the_ direction af the DirectorMear-Training-and-shah-meet-or-exceed-the-l intent of_Section 27 of the NEPA Code-1975,-except-for-Fire-Brigade-training" sessions which sh:11 he held at least nuarterly.

6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

FUNCTION 6.5.1.1 The PORC shall function to advise the Nuclear Station Director on l

all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PORC shall be composed of the:

U 9irperson:

Nuclear Station Director

" aaer:

Nuclear Unit Director

' ember:

Operations Manager Member:

Maintenance Manager Member:

Instrument and Control Manager Member:

Reactor Engineer Member:

Engineering Manager Member:

Nuclear Services Director Member:

Plant Quality Services Supervisor Member:

Chemistry Manager Member:

Health Physics Manager Member:

Security Manager 6-5 Amendment No. JJJ, JJJ,155

/j'i l

'/

HADDAM NECK caso

09/25/92

~ ' ADMINISTRATIVE CONTROLS i.

Review of the Security Plan and implementing procedures and shall submit recommended changes to the Chairperson of the Nuclear Review Board; j.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairperson of the Nuclear Review Board; AUTHORITY 6.5.1.7 The PORC shall:

Report to and be advisory to the Nuclear Station Director on those l

a.

areas of responsibility specified in Section 6.5.1.6(a) through (j);

r-b.

Render determinations in writing to the Nuclear Station Director if any item considered under Specification 6.5.1.6a. through d.,

above, as appropriate and as provided by 10CFR50.59 or 10CFR50.92 constitutes an unreviewed safety question or requires a significant hazards consideration determination.

Provide written notification, meeting minutes may be used for this c.

purpose, to the Executive Vice President-Nuclear and the Chairperson of the Nuclear Review Board of disagreement between the PORC and the Nuclear Station Director; however, the Nuclear Station Director shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The PORC shall maintain written minutes of each meeting that, at a minimum, document the results of all PORC activities performed under the responsibility and authority provisions of these Technical Specifications.

Copies shall be provided to the Executive Vice President-Nuclear and l

Chairperson of the Nuclear Review Board.

6.5.2 NUCLEAR REVIEW BOARD (NRB)

I OUALIFICATIONS 6.5.2.1 The minimum qualifications of NRB members are as follows:

a.

The Chairperson and NRB members shall have:

1.

an academic degree in engineering or physical science field, or hold a senior management position, and 2.

a minimum of five years technical experience in their respective field of expertise, and 3.

a minimum of nine (9) years combined academic and technical experience.

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