ML20211E198

Summary of 860519 Meeting W/Util Re Proposed Changes in Administrative & Reporting Requirements Tech Specs Contained in 820723,830502,850709 & 0813 applications.Marked-up Rev to Tech Specs for Fire Protection Sys Encl

ML20211E198
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/10/1986
From:	Frank Akstulewicz Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8606130278
Download: ML20211E198 (33)

Text

, June 10,1986 DISTRIBUTION, g o

C 7 Docket Fileg

. " NRC PDR Docket No. 50-213 Local PDR ISAP Reading C. Grimes F. Akstulewicz LICENSEE: Connecticut Yankee Atomic Power Company

{LD FACILITY: Haddam Neck Plant B. Grimes ACRS (10)

SUMMARY

OF MAY 19, 1986 MEETING WITH UTILITY D. Haverkamp, RI REPRESENTATIVES CONCERNING ADMINISTRATIVE AND REPORTING TECHNICAL SPECIFICATIONS On May 19, 1986, I met with Mr. J. Powers of the licensee's staff to discuss the proposed changes in administrative and reporting requirements technical specifications contained in their applications dated July 23, 1982, May 2, 1983, July 9, 1985, and August 13, 1985. The proposed changes would add a reference to a new containment isolation valve that has been installed at the facility; make several changes to clarify or correct administrative sections of the technical specifications, and incorporate the reporting requirements of 10 CFR 50.72 and 50.73.

During the review of the proposed changes, Region I personnel identified several areas where additional editorial changes were required to account for amendments, which have been issued since the August 1985 application, and to modify certain existing technical specifications for consistency. In particular, additional changes to the reporting requirements were required in the technical specifications concerning post accident radiation monitors and radiological effluents because these amendments have been issued since the original applications were received. In addition, the proposed changes to the fire protection technical specifications were found to be too limited in scope, therefore, additional proposals for reporting needed to be included.

During this meeting, Mr. Powers and I discussed and agreed to all the changes suggested by Region I, with the exception of the proposed modifications to the technical specification concerning fire protection. Mr. Powers and I prepared a revised technical specification for the fire protection systems, which was discussed with Region I personnel and found to be acceptable. A complete set of technical specifications, including the revisions, is attached.

Original signed by: Frank Akstulewicz Frank M. Akstulewicz, Project Manager Integrated Safety Assessment Project Directorate Division of PWR Licensing - B cc: See next page I

ISAP:DPL-B[jfd IS B P:DPL-B FAkstulewin:mn pan i n f(CGrimes 06/p/86 06//o/86 06/p /86 8606130278 860610 PDR ADOCK 05000213 P PDR

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UNITED STATES NUCLEAR REGULATORY COMMISSION

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5 l WASHINGTON, D. C. 20555

%,,,,,# June 10,1986 Docket No. 50-213 LICENSEE: Connecticut Yankee Atomic Power Company FACILITY: Haddam Neck Plant

SUMMARY

OF MAY 19, 1986 MEETING WITH UTILITY REPRESENTATIVES CONCERNING ADMINISTRATIVE AND REPORTING TECHNICAL SPECIFICATIONS On May 19, 1986, I met with Mr. J. Powers of the licensee's staff to discuss the proposed changes in administrative and reporting req'uirements technical specifications contained in their applications dated July 23, 1982, May 2, 1983, July 9, 1985, and August 13, 1985. The proposed changes would add a reference to a new containment isolation valve that has been installed at the facility; make several changes to clarify or correct administrative sections of the technical specifications, and incorporate the reporting requirements of 10 CFR 50.72 and 50.73.

During the review of the proposed changes, Region I personnel identified several areas where additional editorial changes were required to account for amendments, which have been issued since the August 1985 application, and to modify certain existing technical specifications for censistency. In particular, additional changes to the reporting requirements were required in the technical specifications concerning post accident radiation monitors and radiological effluents because these amendments have been issued since the original applications were received. In addition, the proposed changes to the fire protection technical specifications were found to be too limited in scope, therefore, additional proposals for reporting needed to be included.

During this meeting, Mr. Powers and I discussed and agreed to all the changes suggested by Region I, with the exception of the proposed modifications to the technical specification concerning fire protection. Mr. Powers and I prepared a revised technical specification for the fire protection systems, which was discussed with Region I personnel and found to be acceptable. A complete set of technical specifications, including the revisions, is attached.

arad YYb Frank M. Akstulewicz, Project Manager Integrated Safety Assessment Project Directorate Division of PWR Licensing - B cc: See next page

Mr. John F. Opeka Connecticut Yankee Atomic Power Company Haddam Neck Plant CC:

Gerald Garfield, Esquire Kevin McCarthy, Director Day, Berry & Howard Radiation Control Unit Counselors at Law Department of Environmental City Place Protection Hartford, Connecticut 06103-3499 State Office Building Hartford, Connecticut 06106 Superintendent Haddam Neck Plant Richard M. Kacich, Supervisor RDF #1 Operating Nuclear Plant Licensing Post Office Box 127E Northeast Utilities Service Company East Hampton, Connecticut 06424 Post Office Box 270 Hartford, Connecticut 06141-0270 Edward J. Mroczka Vice President, Nuclear Operations Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141-0270 Board of Selectmen Town Hall Haddam, Connecticut 06103 State of Connecticut Office of Policy and Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106 Resident Inspector Haddam Neck Nuclear Power Station c/o U.S. NRC East Haddam Post Office East Haddam, Connecticut 06423 -

Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406

Docket 50-213 .

Attachment 1 Haddam Neck Plant Proposed Revisions to Technical Specification marneo TritS COPY ut) By M4 rod I

% $ flow A c c.<*P T%b LE wbf2D o ^4 NO pg<,e w see.ma August,1985

INDEX .

DEFINITIONS SECTION 1.0 DEFINITIONS

_ PACE

' . .'.acd Terms f

1-1 1.2 Thermal Power 1-1 1.3 Rated Thermal Power 1-1 4

't .6 Ooerational Mode 1-1 1.5 1-1 1.6 Operable - Operability 1-1 1.7 Reportable Event .

1-2 1.8 Containment Integrity 1-2 1.9 Channel Calibration 1-2 1.10 Channel Check 1-2 . -

1 II Channel Functional Test 1-3 1.12 Core Alteration 1-3 5 ?? Sh:t 'cwn Margin 1-3 1.14 Identified Leakage 1-3 1.15 Unidentified Leakage 1-3

, 1.16 Pressure Boundary Leakage i 1-4

! .17 Controlled Leakage 1-4 1.13 Quadrant Power Tilt Ratio

1-4 I

40 s 1-4 1.20 1-4 1.21 Frequency Notation 1-c 1.22 i 1-5

1.23 -

. 1-5 1.24 Flux Difference

. 1-5 1.25 Lower Power Physics Tests 1-3 Table 1.1 Operational Modes 1-6 Table 1.2 Frequency Notation 17 .. .-.

INDEX AD\t!NISTR ATIVE CONTROLS SECTION 6.0 ADMINISTR ATIVE CONTROLS PACE 6.5.2.4 Consultants .

6-9 6.5.2.5 Meeting Frequency 6-9 6.5.2.6 Quorum 6-9 6.5.2.7 Review 6-10 6.5.2.3 Audits 6-11 6.5.2.9 Authority 6-11 6.5.2.10 Records 6-12 6.5.2.1 I Qualifications 6-12 6.6 REPORTABLE EVENT ACTION

• 6-13 6.7 SAFETY LIMIT VIOLATION ~'

6-13 6.3 PROCEDURES 6-13 6.9 . REPORTING REOUIREMENTS 6.9. l ' ROUTINE REPORTS 6-15 6.9.2 SPECIAL REPORTS

• 6- Q D

_6.10 RECORD RETENTION

~

6.11 6-1(\)

RADIATION PROTECTION PROGRAM 6- % \g 6.12 RESPIRATORY PROTECT!dN PROGRAM (DELETED)

_6.13 HIGH RADIATION AREA

_6.14 6-k13 ENVIRONMENTAL OUALIFICATION 6.15 6- R @

SYSTEMS INTECRITY

_6.16 6-K o IODINE MONITORING 6-KJO

.s l .

t I

DEFINITIONS 1.7 A reportable event shall be any of those conditions specified in Section 30.73 to 10CFR Part 30.

CONTAINMENT INTEGRITY 1.5 CONTAINMENT INTEGRITY shall exist when:

1.E.1 The containment automatic isolation valve system is OPERABLE.

1.8.2 All penetrations required to be closed during accident conditions are either:

a.

Capable of being closed by OPERABLE containment automatic isolation valves, or b.

Closed by manual valves, blind flanges, or deactivated automatic valves secured and locked in their closed positions, 1.3.3 All equipment hatches are closed and sealed, and 1.3.4 Each door in each air lock is closed and sealed except when the air

.. lock is being used for normal transmit entry and exit through the containment, sealed.

then at least one air lock door shall be closed and

_ CHANNEL CALIBR ATION 1.9 A CHANNEL CAi.IBRATION shall be the adjustment of channel output

. such that is responds, with acceptable range and accuracy, to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip.

CHANNEL CHECK

• 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication with other indications derived from independent instrument channels measuring the same parameter.

e e e e

(1) With one relief train inoperable, either restore that train within 7 days, or depressurize and vent the RCS through a minimum 3 inch diameter or equivalent opening within the next 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />; maintain the RCS in a vented condition until both relief trains have been restored to operable status.

(2) With both relief trains inoperable, depressurize and vent the RCS through a minimum 3 inch diameter opening within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />; maintain the RCS in a vented condition until both relief trains have been restored to operable status.

p <5 J 4o sp.e.te.4;.. G.G.t (3) A report ^shall be prepared and submitted to the Commission if either action (1) or (2) is used to mitigate inoperability of one or both relief trains.

F. Whenever the reactor is in Mode 3 the following conditions sha!! be met:

1. At least two of the reactor coolant loops listed below shall be OPERABLE:

a. Reactor Coolant Loop (1) and its associated steam generator and reactor coolant pump,

b. Reactor Coolant Loop (2) and its associated steam generator and reactor coolant pump,

c. Reactor Coolant Loop (3) and its associated steam generator and reactor coolant pump,

d. Reactor Coolant Loop (4) and its associated steam generator and reactor coolant pump.

2. At least one of the above coolant loops shall be in operation.

a. With less than the above required reactor coolant loop OPERABLE, restore the required loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. With no reactor coolant loop in operation, suspend a!!

operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to opration.

G. Whenever the reactor is in Mode 4 or 5 the following conditions shall be met: .

1. A t least two of the coolan t loops listed below shall be OPERABLE:

a. Reactor Coolant Loop (1) and its associa ted steam generator and reactor coolant pump, Haddam Neck 1 ',

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w 3;22 FIRE PRCTTECTION SYSTD'.S rt M] * ' r4 %5'.MT

_ Applicability l

! This specification applies to the operational status of th plant fire protection and detection systems.

e Objeetive To ensure the availability of the fire protection and detectio systems.

n Specification A.

Fire Suppression Water Svstems A.1 The Fire Suppression Water System shall be operable during all modes of operation with:

a)

Two high pressure fire pumps, each with a capacity of 2500 gps, with their discharge aligned to the fire' suppression header.

b)

Automatic initiation logic for each fire pump.

A.2 From and af ter the date that one fire pump is determined to be inoperable, restore the pump to operable status within 7 days or prepare and submit a ^ ~

S tec' a \ t

• within 30 days of the occurrence outlining .the plans and . . p --

procedures to be used to provide for the loss of redundancy in this system.

A.3 From and after the time that the entire Fire Suppression Water System mode:

in any operating is determinedl toA noperable with the plant La l

a) "N C4 tC ,a.511. u av e -

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-th; c.n ione rm _7 -.J.1 :3;y

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--d-eehedwl f:: rect: ring t: - . fie ^:=wc; er -h:-.,,.., #

b)

The plant shall be placed in at ' cast llot Standby within following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 24 hours. and in Cold Shutfovn '

within the

-&e JUS?q d 3-41

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R<yn.J. %.sl~.k. e9 fie eved Ly le)<gke wa A e~L&w I,, fe/c,yL , waitph or EscsikiIe koswssk no I.4< ik tie. ftrsMhvi day -Alb owy fle eveab.

h.' lo:L 14 day -A6 wniy +1e eueah, prepare and sL2 a p seah e

Rycu+ p u.<suad -k 5pcs SLh4 4.?.2., Jin) fie acAw.s kh, fAe cause 04

+te mlMW ns L place and sekedde fx resh<wj tio syskm A gerrWe

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B.

A&ap%tM (M -Cor - Mo MR Carbon Dioxide Svstems w qI h ,) ,

'*%Y j j

B.1 The following CO2 Systems shall be Operable with the i indicated, connected  !

minimum number of bottles of CO2 and available for service and having at least 90% l of full charge veight, whenever the protected equip =ent in the area is required to be Operable:

a) Cable Vault (18) b) Pri=ary Auxiliary Building Charcoal Tilters (8) i B.2 Trom and after the time a CO2 system listed in B.1 is deter =1ned to be inoperable, within one hour I establish a continuous fire watch with backup fire suppression equipment for the unprotected equipment and/or area.

• i Sp4(J <. i f B.3 Restore the system to Operable status "

within 14 days or prepare and submit a "- ..: Report to the Commission pursuant to Specification 6.9.2 % thin j 30 days of the occurrence out11ains the cause of the inoperability and the plans for restoring the system to Operable status.

C. Halon 1301 System C.1 The Halon 1301 System for the switchgear room shall be operable with at least (7) Halon bottles connected and available for service and each bottle shall be

.. ", at least 9_2%

2 of full charge weight.

C.2 Trom and after the time the Halon system listed in C.1 is deter =ined to be inoperable within one hour establish a continuous fire vacch with backup fire suppression equipment for the unprotected equipment and/or area.

Meio\

C.3 Restore the system to operable status " within 14 days or prepare and submit a L - Report to the Comnission pursuant to Specification 6.9.2 [ ithin 30 days of the occurrence outlining the cause of the inoperability and the plans for restoring the system to operable status.

D. Fire t'acer Stations _

D.1 The Fire *'acer Stations listed in Table 3.22-1 shall be Operable.

i

_ _ _ _ _ _ _ _ _ - _ __ _ . . _ . _ _ _ . .knendment

. _ . , _ . ~ ' _No._ 24, 23, 45

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A c c e_ p v u (L do ~b. m & m e o, y,W wwA w_pA 9 .g, &

D.2 From and after the time any of the Fire Water Stations listed in Table 3.22-1 are determined to be inoperable, within one hour route an additional equivalent capacity hose to the unprotected area from an operable fire water station or establish a fire patrol to inspect the unprotected area at intervals of at least once each hour.

E. Fire Detection Syste=s E.1 The mini =u= nu=ber of detectors for each fire detection zone shown in Table 3.22-2 shall be OPERABLE.

E.2 ACTION Whenever the nu=ber of OPERABLE detectors is less than the mini =t.=1 nc=ber OPERABLE requirement of Table 3.22-2:

a. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire vacch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect the containment 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 at least once per hour at the locations referenced by Specification 4.4, Contai=sent Testing) .

. b. Restore the inoperable instrument (s) to OPERABLE status within 14 days, or, prepare and submit a

) Special Report to the. Commission pursuant to

, Specification 6.9.2)Pulthinthenext30 days g outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrument (s) to OPERABLE status.

F. Penetration Fire Barriers F.1 Penetration fire barriers (including cable penetration barriers, fire doors and fire dampers) that protect safety related areas shall be functional.

F.2 Fron and af ter the time that it is determined that a penetration fire barrier is not functional; (a) the areas shall be monitored by operable fire detectors and within one (1) hour a fire vacch patrol shall be established to inspect the area of at least once per hour or (b) a continuous fire vacch shall be established on at least one side of the affected penetration within one (1) hcur.

3-43 Amendment No. 2A, 23, 45

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N K (. Qsj , ,, _ e M y.4 r A e e e r'-W 'i C '-

C.2 Frez and af ter the N wc t

• d -t L 'd-3 'tWo'* s% e-L). ',m c.CC time any of the spray and/orprinkler-

• syste=a listed in G.1 is dete==ined to be isoperable, d within one hour, establish a continuous fire watch with backup . fire suppression for those areas starred (*) in -

G.1; for other areas, establish a fire patrol to inspect the applicable unprotected area at intervals of at least once each hour.

. Sp< ch \

C.3 Restore the ' inoperable system to operable scath,s within 14 days or prepare and submit a h1Weer-Report

• I 7

to the Cc==ission pursuant to Specification 6.9.2f7 within 30 days of the occurrence outlining the cause of the inoperability and plans for restoring the inoperable system to operable status.

Basis A. Fire Detection and Suppression Systems Fire Suppression Systems -

The operability of the fire suppression systems ensures that adequate. fire suppression capability is available to confine and extinguish fires occurring in any portion of the facility where safety related equip =ent is located. 'The_ fire suppression system consists of tha veter systema, spray and/or sprinklers, CO2 Syste=s, Halon 1301 Syste=s, fire hose stations and hydrasts. The capability of the fire suppression syste=s is adequate to minimize potential damage to safety related equipeent and is a major ele =ent in the facility fire protection program.

In the event that a portion of the Fire Suppression System beco=es inoperable, alternate backup fire fighting equipment or a periedic fire watch patrol is required to be established in the associated area until the inoperable equipment can be restored to service.

In the event that the fire suppression water system becc=es inoperable, i==ediate corrective =casures =ust be taken since this syste= provides the major fire suppression capability of the plant. The require =ent for a twenty-four hour repert to the Cc cission provides for pre =pt evaluation of the acceptability of the corrective =casures to provide )

adequate fire suppression capability for the continued l protection of the nuclear plant.

I(

Amendment 24, 23, 45

~

3-44a

~

3.$3 Psse Accident Inst rumtntn t ien

., Aeolicability Thisspecificationappliestospebificplant inst rumentation

(' -

required for post-accident assessments.

Obj ec tive To ensure the instrumentation will be operable if required.

Soecification A.

Containment Hich Radiation Monitor A.1 Two containment high radiation monitor channels shall be operable during modes 1, 2, 3, and 4 with:

a) The capability to measure up to 1 x 100 R/hr.

• b) The alarm setpoint less than or equal 100 R/hr.

A.2 Vith one or more channel (s) inoperable, restore the inoperable channel (s) to operable status '

uithin 7 days, or else prepare and submit a Special Report to the Commission pursuant to

( '

Specification 6.9.

outlining:

within the next 10 days the c use of the malfunction, the plans for re toring the channel to operable status, and any leernative methods for esti-mating containment f

dose rates during the interim.

R .

-- ----a

B. _Strek Vide Range Noble Gas Monitor B.1 One stack wide range noble gas monitor channel shall be

• operable during modes,.1, 2, 3, and 4 with:

a) The capability to measure up to 1 x 105 pC/cc of Xe-133.

b) The alarm setpoint 3,ess than or equal to the moni. tor reading corr'esponding to 1 pC/cc.

B.2 With less than one channel operable, return one channel to operable status within 7 days, or else prepare and submit a Special Re ort to the Co==ission pursuant tc Specification 6.9.

gg -

ause of within the next 10 days outlining:

malfunction, the plans for restoring tne channel to operable status, and any alternative methods interim. for estimating stack release rates during the i:

Basis These specifications ensure the operability of the high range containment radiation monitors and wide range stack noble gas monitors.

ments.

These monitors are required for post-accident assess-This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled

, Nuclear Power Plants to Assess Plant and Environs Conditions

- During and Following an Accident", December 1980 and NUREG-0737

" Clarification of TM1 Action Plan Requirements," November,1980.

l. .

3-46 Amendment No. 66

1 I

COWr.CTICL7 YA.92E ATO.1IC PO'-TR CO.4P/JT

_OTTSITE ORGANIZATION .

I CYAPCO Chairman I hTSCO Chairman and I Chief Executive Officer

• 1 i

CYPACO President hTSCO Pres 2 dent and Chief Operating  !

Officer CYAPCO Executive Vice President and Chief Onerating Officer hTSCO Executive Vice President Engineering and Operations

' E, CYAPCO Senior Vice President i

- hTSCO Senior Vice Prestdent Nuclear Engineering and

• Operations

-}

l I 5 l I

' Nuclear Review Board Northeast Utilities >

Service Co=pany (hTSCO)* [ '

l s

CYAPCO Vice President i n

hTSCO Vice President I Nuclear Operations '

i i!

Nuclear Opera tions OI Staff Connecticut Yankee Station [!

Superintendent - Onsite

{

• Provides Opera ting and Technical Support by Contractual Arrangement Figure 6.2-1 v a nn . . ..

AD.MINISTRATIVE CONTROLS 6.5.2 .

NUCLEAR REVIEU BOARD (NP3)

FUNCTIOS '

6. 5. 7. ! The Nuclear Revleu Board provide independent shall function to ,

the areas of: Jrevieu and audit of designated activities in I

a. nuclear power plant operationc J

b. nuclear engineering ';

r

c. chemistry and radiochemistry I

d. metallurgy

e. nondestructive testing \ b

f. in:tr==entation and control

g. radiological safety p

1. c'echanical and electrical engineering s 0

i. administration i t,

j. quality assurance practices b

.t.

t

. t i

c. .

t k'li 9.

14 .

j 6-8

2 AD.9 NISTEATIVE CONTROLS 3

us.ausa>10N 6.5.2.2 The NR3 shall consist of no less than seven, nor more than eleven me=bers including the Chairman and the Station  !

Superintendent.

The Chairman and members of the NRB shall [

be appointed in vriting by the Senior Vice President - Nuclear Engineering and Operations, and shall have an acade=1c degree d in engineering or phy,sical science field or equivalent ex- j.l perience. Technical ~ experience in the areas specified in j; Section 6.5.2.1 may be substituted on a one-for-one basis towards the acade=le degree requirement. (Four years of 8 i technical experience being equivalent to a four-year acade=ic j g

degree.) In addition, they shall have a mini =um of five years technical experience, of which a minimum of three s

years shall be in their respective field of expertise.'To4nd i t ac de.wk Gwa +#Ch" M CV-Pd"Ic^<C' *% M b k

• A. um i mwm o+ m n e . 3 e a(t. S. .

CONSULTANTS d 6.5.2.3 Consultants shall be utilized as determined by the NRB Chair =an L d

. p. vide expert advice to the NR3. l MEETINC FREQUENCY i, . ,

L L 6.5.2.4 The NR3 shall meet at least once per six months. hi l

.S.

OUORLH Ih

\.ii

't.  !

6.5.2.5 ^

, The minimum quorum of the NRB necessary for the perfor=ance of () ;

t the NRB review and audit functions of these Technical Specifications l 4& i shall consist of the Chair =an or his designated alternate and .at least four (4) NRS me=bers. No more than a minority of the quoru=

shall have line respor.sibility for operation of the facility. .

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6-9

ADMINISTR ATIVE CONTROLS R EVIE W 6.3.2.6 The NRB shall review: t a.

The sa,fety evaluations for 1) changes'to procedures, equipment or  !

systems30.39, Section and 2) 10tests or experiments completed under the provision of p

CFR, an unreviewed safety to verify that such actions did not constitute question. f h

b. j l Proposed changes to procedures, equipment or systems which involve  ;  ;

an unreviewed safety question as defined in Section 30.39,10 CFR. [ t

c. i Proposed tests or experiments which involve an unreviewed safety question as defined in Section 30.39,10 CFR.

d.

Proposed changed in Technical Specifications or licenses.

c. i Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal enocedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from normal and I expected performance of plant equipment that affect nuclear safety. E

g. All reportable events. f f

h. H l

Indications of a significant unanticipated deficiency,. . affecting 1 nuclear safety, in some aspect of design or operation of safety related structures, systems or components.

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i. Reports and meeting notes of the PORC. 4 11 Y

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!!i Haddam Neck 6-10

ADMINISTRATIVE C0!.*TROLS AUDITS i

6.5.2.7  ;

Audits of facility activities shall be perfor=ed under the cognizance of the NRB. These audits shall encompass:

a.

. The conformance of unit operation to provisions 1 contained within the Technical Specifications and i applicable license conditions at least once per [

12 months.

l j b.

The perfor=ance, training and qualifications of the en < '

facility staff at least once per 12 months. l

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c.

The results of actions taken to correct deficiencies l occurring in facility equipment, structures, systems or method of operation th i it affect nuclear safety at least j once per six months. j '

r d.

The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix l }

"B",

10 CFR 50, at least once per 24 months.

j e.

The E=ergency Plan and implementing procedures at least l once per 24 months. [ j

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. f. t I The Security Plan and implementing procedures at least u once per 24 months.

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I g.

Any other area of facility operation considered appropriate i by the and NRB or the Senior Vice President-Nuclear Engineering Operations. i P

h.

The Fire Protection Program and implementing procedures I i at least once per 24 months. -

l 1.

An inspection and audit of the Fire Protection and loss I prevention program shall be perforced at least once per I 12 months by an outside firm experienced in fire protection and loss prevention.

AIITHORITY 6.5.2.8 p!

The NRE shall report to and advise the Senior Vice President-Nuclear specifiedEngineering and Operations on those areas of responsibility in Section 6.5.2.6 be used for this purpose.

and 6.5.2.7. Meeting minutes may El:

l 6-11

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• ADMINISTR*TfvE CONTRDts -

• RECORDS [

>6.5.2.I Records of HRB activities shall be prepared, approved and distributed as indicated below: l a.

Minutes of each NRB meeting shall be prepared, approved and -

9 forwarded to the Senior Vice-President-Nuclear Engineering and Oper,ations within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.6. I 1

above, shall be prepared, approved and forwarded to the Senior Vice President-Hucliar Engineering and Ooerations within 14 days following completion of the review. . ,

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c. Audit reports encompassed by Section 6.5.2.7 above, shall be i forwarded to the Senior Vice President-Nuclear Engineering and Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit.

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4 ADMINISTR ATIVE CONTROLS t,. e KEPORTABLE EVENT ACTION - 3 6.6.1 .

The following actions shall be taken for Reportable Events:

a. ,

The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 30.73 to 10CFR Part 50 and b.

Each Reportable event shall be reviewed by the PORC and submitted to the NRB and the Vice President Nuclear Operations.

6.7 SAFETY LIMIT VIOLATION ~~~

6.7.1 The fo!!owing actions shall be taken in the event a Safety Limit is violated.

a.

The unit shat! be placed in at least HOT STANDBY within one hour. l y

b.

The NRC. Operations Center shall be notified by telephone as soon .

as possible and in all cases within one hour. The Vice President l

.'h.: clear Operations and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ,

c.

A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC.

This report shall describe (1)

' applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) )'

corrective action taken to prevent recurrence.

d. }-

The Safety Limit Violation Report shall be submitted to the Commission, within 14 days the NRB of the and the Vice President-Nuclear Operations violation. -f t '

6.3 _ PROCEDURES 6.S.! Written procedures and administrative i policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Section l 3.1 and 5.3 of ANSI N18.7-1976 and Appendix "A" of 6.S.2 and 6.3.3 below.

USAEC Regulatory Guide 1.33 except as provided in Procedures shall be established and maintained for implementation of the Facility Fire Protection Program.

6.S.2 ,,

Each procedure and administrative policy of 6.S.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Statio n [

Superintendent each document. prior to implementation and periodically as set forth in [

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Haddam Neck 6-13

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i 6.9 REPORTING REQUIREMENTS

..:J; tion to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be s'ubmitted .

to the regional administrator of the appropriate Regional Office unless ot5erwise noted.

6.9.1 Routine Reoorts i

a.

Startuo Report - A summary report of plant startup and I power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been l manufactured l by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

The report shall address each of the tests identified in the l FSAR and shall in general include a description of the j measured values of the j operating conditions or characteristics obtained during the test program and a l comparison of these values with design predictions and specifications.

3 Any corrective actions that were required to obtain satisfactory operation shall be described. Any

• additional specific details required in license conditions d based on other commitments shall be included in this report. a

, at f

Startup reports sha!! be submitted within (1) 90 days j following days completion of the startup test program, (2) 90 3 fo!!owing resumption or commencement of  ;

commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup i

Report does not cover a!! three events (i.e., initial  %{

criticality, completion of startup test program, and l resumption or commencement of commercial power operation), supplementary reports sha!! be submitted at least every three months until all.three events have been y completed. l b.

Steam Generator Tube Inspection - The complete results of the steam generator tube inservice inspection shall be ,

l reported within ninety days after completion of the ,;

inspection. This repori shall include:

y' '

1) number and extent of tubes inspected. i*

2) -

l Location and percent of wall thickness penetration for each indication of an imperfection.

3) Identification of tubes plugged.

l Haddam Neck 6-15 l

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c. Occucational Exoosure Recort The annual report shall be submitted prior to March I of.rach year and shall cover the previous calendar year. The initial report shall i be submitted prior to March 1 of the year following initial j criticality.

4 This annual report shall include a tabulation on an annual basis of d

the number of station, utility, and other personnel (including 1 contractors) receiving exposures greater than 100 mrem /yr. and their associated man-rem exposure according to work and job functions, 4 c.g., reactor operations and surveillance; inservice inspection, routine maintenance, special maintenance (describe I

maintenance), waste processing and refueling. The dose l assignment to various duty functions may be estimated based on  !;

pocket dosimeter, TLD, or film badge measurements. Small l exposures totalling less than 20% of the individual total does need j not be accounted for. In t.he aggregate, at least 30% of the total j whole body dose receive from external sources shall be assigned to specific major work functions. i

d. Monthly Operating Report - Routine reports of operating statistics L

and shutdown experience shall be submitted on a monthly basis to [

the Director, Office of Management Information and Program Control, U. S. Nuclear Regulatory Commission, Washington, D. C. '

20553, with a copy to the appropriate Regional Office, to be ,

postmarked no later than the fif teenth of each month following the calendar month covered by the report.

The monthly report sha!! include a narrative summary of operating experience during the report period relating to safe operation of the facility, including safety-related maintenance.

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e. Reports required as per 10 CFR 50.59b.

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Haddam Neck 6-16

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ADMINISTR ATIVE CONTROLS SPECIAL REPORTS '

6.9.2 Special reports sha!! be submitted to the Regional Administrator of the appropriate regional office within the time period specified for each report. These reports shat! be submitted covering the activities identified below pursuant to the requirements of the  ;

applicable reference [~pecification:

a. inservice Inspection results,[pecifications (4.10) and (4.12). j l

b. Primary Containment Leak Rate Results, Specification (4.4). i  ;

1 .

c. Reactor Vessel Material Survei!!ance Specimen Examination, hl Specification (4.10).  !  !

.l

d. Steam Generator Tube Report. l l

Following each inservice inspection of steam generator tubes, the  !

number of tubes plugged in each steam generator shall be reported to the Commission within 15 days.

T- E. A(,.23 - 8moac. tsj

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6.10 RECORD R TENTION l

' ' 6.10.1 The following records shall be retained for at least five years: , ,

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a. Records and logs of facility operation covering time interval at each power level.

i

b. Records and logs of principal maintenance activities, y inspections, repair and replacement of principal items of 3 equipment related to nuclear safety. L

c. All Reportable !! vents.  :

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

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ADMIN!5TR ATIVE CONTROLS . -l

e. Records or reactor tests and experiments.

f. Records of changes made to Operating Procedures. s

g. Records of radioactive shipments.

h. Records of sealed source leak tests and results.

4. .% cords of annual physical inventory of all source material of record.

j. Radiation and contamination surveys.

6.10.2 The fo!!owing records sha!! be retained for the duration of the I Facility Operating License:

f 1

a. Record and drawing reflecting facility design j changes modifications r.ude to systems and equipment described in the I:

Facility Description and Safety Analysis Report. f I

b. . Records of new and irradiated fuel inventory, fuel transfers and j assembly burnup histories, k y

c. Records of facility radiation and contamination surveys. '

d. Records of radiation exposure for all individuals entering radiation (

control areas. 4,

c. Records and gaseous and liquid radioactive material released to the ,

environs, j

.1

f. Records of transient or operational cycles for those facility (

components designed for a limited number of transients or cycles. l; ,

f 4 l g. Records of training and qualification for current members of the [

plant staff. *

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h. Records of in-service inspections performed pursuant to these I; Technical Specifications, j

i. Records of Quality Assurance activities required by the QA  :

Manual, t, f'

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 30.59. f ,

. i 5,.

k. Records of meetings of the PORC and the NRS.

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1. Records for Environmental Qualification which are covered under  ;

the provisions of paragraph 6.14 6 -18 Haddam Neck 19

l ADMINISTR ATIVE CONTROLS 6.11 R ADIATION PROTECTION PROGR AM Procedures for pe'rsonnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained an'd adhered to for all operations involving personnel radiation exposure.

6.12 SUPERSEDED BY 10 CFR 20.103(c) AND (f) ON DECEMBER 28,1977 6.13 HIGH R ADIATION AREA 6.13.1 i In lieu of the " control device" or " alarm signal" required by paragraph j 20.203(c)(2), each high radiation area in which the intensity of radiation is 1000 l mrem /hr or less sha!! be barricaded and conspicuously posted as a high radiation  :

area and entrance thereto sha!! be controlled by requiring issuance of a j Radiation Exposure Authorization *. An individual or group of individuals j ,

permitted to enter such areas shall be provided with one or more of the ]

following: ,

a. A radiation monitoring device which continuously indicates the ,

radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the g radiation dose rate in the area and alarms when a preset integrated [

dose is received. Entry into such areas with this monitoring device }

may be made af ter the dose rate level in the area have been t

[

established and personnel have been made knowledgeable of them.

c. A health physics qualified individual (i.e. qualified in radiation protection procedures) with a radiation dose rate monitoring device }p who is responsible for providing positive control over the activities q within the area and who will perform periodic radiation p surveillance at the frequency specified in the REA. The L l surveillance frequency will be established by the Health Physics l l Supervisor. . {d The t.tove procedure sha!! also apply to each high radiation area in which the  ;'

intensity of radiation is greater than 1000 mrem /hr. 'In addition, locked doors '

shall be provided to prevent unauthorized entry into such areas and the keys shall 4 l be maintained under the administrative control of the shif t supervisor on duty.

• Health Physics personnel sha!! be exempt from the REA issuance requirement

]h l- if during the performance of their assigned radiation protection duties, providing lf they are following plant radiation protection procedures for entry into high }

radiation area < t

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Haddam Neck 20-

ADMINISTR ATIVE CONTROLS .

6.14 ENVIRONMENTAL OUALIFIC ATION

• A.

By no later than June 30, 19S2 all safety-related electrical equipment in the facility shall be qua provisions of Division of Oper ng Reactors ied in accordance with the

" Guidelines for Evaluating Environmental Qua ication of Class IE Elecirical Equipment in Operating Rea ors" (DOR Guidelines); or, NUREG-0533 " Interim Staff Posi Safety-Related Electric n on Environmental -Qualification of Equipment", December 1979. Copies of these documents are DPR-61, dated Oct er tached 24,1980.to Order the Modification of License B. By no later th i December 1,1980, complete and auditable records must be av alable and maintained at a central location which l i describe '

e environmental qualification method used for all l safety- lated electrical equipment in sufficient detail docu to j

ent the degree of compliance with the DOR Guidelines or N EG-0588. -

Therefore, such records should be updated and ,

l aintained current as equipment is replaced, further tested, or otherwise further qualified.

l 6.15 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems I I outside containment that would and could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. , .

This program shallinclude the following: l L

1. Provisions establishing preventive maintenance and periodic .

visual inspection requirements, and [

.[

2. Integrated leak test requirements for each system at a t i frequency not to exceed refueling cycle intervals. l 6.16 _ IODINE MONITORING f(

h

) I The licensee shall implement a program which will ensure the capability 1 -

i to accurately determine the airborne iodine concentration in vital area .

t under accident conditions. This program shall include the following: .

1. Training of personnel, 1 I

2. Procedure for monitoring, and 1 0

, l

3. Provisions for maintenance of sampling and analysis equipmen..  !

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lo ;LO Haddam Neck 4-24 .

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RADIOACTIVE EFFLUENTS

( '

DOSE, LIQUIDS ,

0 LIMITIN5 CONDITION FOR OPERATION -

7.1.1.2 The dose or dose commitment to any MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the site sha!! be limited: .

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or e<jual to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

APPLICABILITY: At all times.

ACTION: g

a. With the calculated dose from the release of radioactive materia in liquid effluents exceeding any of the above limits, prepare and su mit to the Commission within 30 days, pursuant to Specification 6.9./, a Special Report which identifies the cause(s) for exceeding tne limit (s) and defines the corrective actions to be taken to reduce the releases

(.

of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC from such release during the calendar year is within 3 mrem to the total body and 10 mrem to any organ.

SURVEILLANCE REQUIREMENTS .

3.1.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with Section II of the REMODCM. -

3.1.1.2.2 Relative accuracy or conservatisms of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the REMODCM.

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HADDAM NECK 7/81-2 Amendment tio.D 0

RADIOACTIVE EFFLUENTS DOSE, NOBLE G ASES LIMITING CONDITION FOR OPERATION 6 .

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7.1.2.2 The air dose offsite due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation;

b. During any calendar year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation; APPLICABILITY: At all times.

ACTION: 3

a. With the calculated air dose from radioactive noble gases

• effluents exceeding any of the above limits, prepare and submit to the Commission within the Report which identifies 30 cause{s) days, pursuant to Specification for exceeding the limit s) and -6.9.f(a S defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of

('

the current calendar quarter and during the remainder of the calendar year so that the cumulative dose during the calendar year is within 10 mrad for gamma radiation and 20 mrad for beta radiation.

SURVEILLANCE REQUIREMENTS 8.122.1- Dose Calculations. Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases sha!! be determined in accordance with Section II of the REMODCM once every 31 days.

8.1222 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in Section 1 of the REMODCM.

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HADDAM NECK 7/81-4 Amendment No.6 8 i

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R ADIOACTIVE EFFLUENTS

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DOSE, R ADIONUCLIDES, R ADIO ACTIVE M ATERIAL IN PARTICULATE FORM, AND l

R ADIONUCLIDES OTHER TH AN NOBLE G ASES - -

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. LIMITING CONDITION FOR OPERATION 7.1.2.3 The dose to any MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium and radioactive materials in particulate form with half lives greater than 8 days in gaseous effluents released offsite shall be limited to the '

following:

a. During any calendar quarter to less than or equal to 7.5 mrem to any organ; 1 b. , During any calendar year to less than or equal to 15 mrem to any organ.

l APPLICABILITY: At all times. -

ACTIONi *

- a. . With the calculated dose from the release of radionuclides, radioactive i

materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and

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submit to the Commission within 30 days, pursuant to Specification j 6.9. a Special Report which identifies the cause(s) for exceeding the 7 amit and defines the corrective actions to be taken to reduce the releases during the remainder of the current calendar quarter and during the remainder of the calendar year so that the cumulative dose or dose commitment to any MEMBER OF THE PUBLIC.from such releases during the calendar year is within 15 mrem to any organ.

SURVEILi.ANCE REQUIREMENTS

. 3.1.2.3.1 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II of the REMODCM once every 31 days.

8.1.2.3.2 Relative accuracy or conservatism of the calculations shall be confirmed by performance of the Radiological Environmental Monitoring Program as detailed in the REMODCM.

t HADDAM NECK 7/81-5 Amendment No.O O

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

o R ADIOACTIVE EFFLUENTS

( 7/8.1.3 TOTAL DOSE .

LIMITIhG CONDITION FOR OPERATION .:.

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7.1.3r The dose or dose commitment to a MEMBER OF THE PUBLIC from the site is limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which is limited to less than or equal to 75 mrem) over a period of 12 consecutive months.

APPLICABILITY: At all times.

ACTION: -

2

a. With the calculated dose from the release of radioacti materials in liquid or gaseous effluents exceeding twice the limi/s of Specification 7.1.1.2.,7.1.2.2., or 7.1.2.3., prepare and suomJ1 y$pecial Report ~to the Commission pursuant'to Specification 6.9. rand limit the

-subsequent releases such that the dose or dose commitment to any MEMBER OF THE PUBl'IC from the site is limited to less than or eq'ual to 25 mrem to the total body or any organ (except thyroid, which is limited to less than or equal to 75 mrem) over 12 consecutive -

months. This Special Report shall include an analysis which

~

demonstrates that radiation exposures to any MEMBER OF THE PUBLIC from the site (including all effluent pathways and direct

(..

radiation) are less than the 40 CFR Part 190 Standard. If the

. estimated doses exceed the above limits, the special report sha!!

include a request for a variance in accordance with the pro' visions of 40CFR190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

SURVE!LI.ANCE REQUIREMENTS 8.1.3 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents and direct' radiation from the site shall be determined in l Specifications 3.1.1.2.1,8.12.2.1 and 8.1.2.3.1 and in accordance with Section 11 of the REMODCM once per 31 days. '

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HADDAM NECK 7/81-6 Amendment No.6 8

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