ML20205D289

Amend 79 to License DPR-61,revising Administrative Sections in Chapter 6 & Tech Specs to Add New Containment Isolation Valve & New Reporting Requirements Consistent w/10CFR50.72 & 50.73

ML20205D289
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/06/1986
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205D280	List: ML20205D276 ML20205D289 ML20205D297
References
NUDOCS 8608150322
Download: ML20205D289 (37)

Text

8 UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION g j WASHINGTON, D. C. 20555

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-61

1. The Nuclear Regulatory Commission (the Comission) has found that:

A. The' applications for amendment by Connecticut Yankee Atomic Power Company (the licensee), dated May 2, 1983, July 9, 1985, August 13, 1985, August 15, 1985, and meeting summary dated June 10, 1986, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common j defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is amended by changes to the technical specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby amended to read as follows:

(2) Technical Specifications The technical specifications contained in Appendix A, as revised through Amendment No. 79, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the technical specifications.

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

, FOR THE NUCLEAR REGULATORY COMMISSION TQ b Christopher I. Grimes, Directo Integrated Safety Assessment Project Directorate Division of PWR Licensing - B

Attachment:

Changes to the Technical Specifications Date of Issuance: August 6,1986 i

ATTACHMENT TO LICENSE AMENDMENT N0. 79 FACILITY OPERATING LICENSE N0. DPR-61 DOCKET N0. 50-213 Replace the following pages of the Appendix A technical specifications with the enclosed pages as indicated. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT i i iv iv v v vi vi 1-1 1-1 3-4a 3-4a 3-20c 3-20c 3-41 3-41 3-42 3-42 3-43 3-43 3-44a 3-44a 3-45 3-45 3-46 3-46 4-21e 4-21e 4-21g 4-219 6-2 6-2 6-8 6-8 6-9 6-9 6-10 6-10 6-11 6-11 6-12 6-12 6-13 6-13 6-15 6-15 6-16 6-16 6-18 ----

6-19 ----

6-20 ----

6-21 6-17 6-22 6-18 6-23 6-19 6-24 6-20 6-25 6-21 6-26 6-22 7/8 1-2 7/8 1-2 7/8 1-4 7/8 1-4 7/8 1-5 7/8 1-5

. 7/8 1-6 7/8 1-6

It!DEX OEFINITIONS .

u SECTION 1.0 DEFINITIONS PAGE 1.? 0FFINED TERMS ........................................... 1-1 1.? TFERMAL POWER ........................................... 1-1 1.3 RATED THERMAL POWER ..................................... 1-1 1.4 OPERATIONAL MODE ........................................ 1-1 1.5 ......................................................... 1-1 1.6 OPERABL E - OPE P.AB IL ITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.7 REP 08 TABLE EVENT:. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.8 CONTAINNENT INTEGRITY ................................... 1-2 1.9 C HAN N EL CAL IB RATI ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 '

1.10 CHANNEL CHECK ........................................... 1-2 1.11 CHA!!!!EL FUNCTI 0t!AL TEST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3

. 1.12 CORE ALTERATION ..........................'............... 1-3 1.13 SHilTP0 Hit KAP. GIN ......................................... 1-3 1.14 IDENT I F I E D L EA KAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3

+

1. 15 UPI DENTI FI ED L EA KAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1.16 PRESSilRE BOUNDARY LEAKAGE ............................... 14 1.17 C0!!TF OL L ED L EA KA G E . . . . . . . . . . . . . . . . . . . . . . . . . . . .,. . . . . . . . . . 1-4 1.18 OUADRANT POWER TILT RATIO ....................'........... 1-4 .

1.19 * .....................................................'.... 1-4 1.20 ......................................................... 1-4 1.21 FREQUENCY NOTATION .....,................................. 1-4 1.22 .........................................................

1-5 1.23 ......................................................... 1-5 1.24 FLUX D I F F EF Et:C E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.25 L OW POWEP PHYSICS TESTS ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1-5 Ta bl e 1.1 Opera t io na l Mo d es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 Ta bl e 1.2 Frequency Nota tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 4

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INDEX .

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. ADMINISTRATIVE CONTROLS t

[ SECTION 6.0 ADMINISTRATIVE CONTROLS PAGE 6.1 RESPONSIBILITY ............................................ 6-1 6/2 ORGANIZATION 6.2.1 Offsite .................................................. 6-1

6. 2. 2 Fa ci l i ty Sta f f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6.3 FACILITY STAFF QUALIFICATIONS ............................ 6-5 T 6.4 TRAINING ................................................. 6-5 6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE ,

[ i. 6.5 1.1 Function ................................................

6-5 6.5 1. 2 Comp o s i ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 f .

6.p 6-6 6.a5 '. l.. 4l He

. lcAti ngl Frequete rna ncyte...s . . ... ... .. . .. ... ... .. . .. ... ... .. . .. ... ... .. . .. ... ... .. . . . 6-6 .. .........

6.5.1.5 Quorum ..................... ............................ 6-6 6.5.1.6 Responsibilities ...........................;............ .

6-6 6.5.1.7 Authority ...........................................,... .

6-7 6 . 5. 1. 8 Re co rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . 6-7 6.5.2 NUCLEAR REVIEW .'80ARD 6.5.2.1 Function ................................'............... 6-8 6.5.2.2 Composition ............................................. 6-9 6 . 5. 2. 3 Co n s u l t a n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-9

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gy Amendment No.,f5,, 79

1 INDEX. -

I ADMINISTRATIVE CONTROLS SECTION 6.0 ADMINISTRATIVE CONTROLS PAGE 6.5.2.4 Meeting Frequency- . .

. . . . . . . . . . . . . . . . . 6-9 6.5.2.5 Quorum . .

. . . . . . . . . . . . . . . . . 6-9 6.5.2.6 Review ' . .

.................6-1c 6.5.2.7 Audits . .

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6-11

^

. .: 6.5.2.8 Authority . .

6-11 6.5.2.9' Records . .

. . '. . . . . . . . . . . . . . . 6-12 6.6 REPORTABLE EVENT ACTIO:4

. . . . . . . . . . . . . . 6-13

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6',7 SAFETY LIMIT VIOLAT10t1 .

........[....... 5-12 6.8 PROCEDURES ,

. . . . . . . .<. . . . . . . . . 6-13 6.9 - REPORTING REOUIREMENTS .

6.9.1 ROUTIhE REPORTS . ,. . . . . . . . . . . . . . . . . . . .

, 6-15

~ 6.3.'2 Specisl . Rep 6rts g . . . . . . . . . . . . . . . . . . . . . 6-18 6.10 RECORD RETENTION . . . .

. . . . . . . . . . . . . . . . 6 18 6.11 RADIATION FROTECTION PROGRAM . . . . . . . . . . . . . . 6- 2 0 6.12 RESPIRATORY PROTECTI0tl PROGRAM (DELETED)

S.13 HIGH RADIATI0tt AREA . . . . ...............620 6.14 ENVIRONMEtiTAL 00ALIFICATiGN (DELETED)

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v Amencment no. JJ 25. 37. //, 79

It!OEX ADNillISTRATIVE CONTROLS SECTION 6.0 ADMINISTRATIVE C0ffTROLS -- Continued PAGE 6.1S SYSTEMS INTEGRITY ..................................... 6 -21 6.16 IODINE NONITORING ............................ ........ 6- 21 6.17 PADIOLOGICAL EFFLUENT N0f1ITORING AND OFFSITE DOSE CALCULATION NANUAL (REMODCM) ..............n ... 6- 22 6.18 RdDI0 ACTIVE WASTE TREATP.ENT SYSTEMS . . . . 6. ..22 . . .. . . . . . . . .

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• e vi, AmendmentNo.g e 79

1.0 DEFINITIONS

_ DEFINED TERitS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

THERNAL POWER 1.2 THERHAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

RATED *DIERMAL POWER 1.3 RATED THERHAL POWER shall be a total reactor core heat transfer

,,. rate.to the reactor coolant of 1825 HWt. ,'-

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OPERATIONAL HODE 1.4 An OPERATIONAL HODE shall correspond to any one inclusive combination of core reactivity condition, power level and gerage reactor coolant temperature specified in Table 1.1.

1.5 yet used, .

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OPERABLE - OPERABILITY -

1.6 A system. subsystem, train component. or device shall be OPERABLE or have OPERABILITY vhen it is capable of performing its design function (s).

> Implicit in this definition shall be the assumption that all attendant instrumentation, controls, elect'ic r power. cooling or s'eal water, i lubrication or other required auxiliary equipment is.also OPERABLE.

REPORTABLE EVENT

). , .l .7 A reportable event shall be any of tho.se conditions spec'ified in L

1 Section 50.73 to 10 CFR Part 50.

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i Amendment No.f6', 79 1-1 l

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(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 l the RCS in a vented condition until both relief trains have been '

restored to operable status.

(2) With both relief trains inoperable, depressurize and ve t 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.

(3) A report pursuant to specification 6.6.1 shall be prepared and submitted to the Comission 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 shall be met:

1. At least two of the reactor coolant loops lisJed'below shall be OPERABLE: ,

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

b. Reactor Coolant Loop (2) an,d itj associated steam Senerator 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 ar.d reactor coolant pump.

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

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a. With less than the above required reactor toolant 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 hoiars' l b. With no rea'ctor coolant loop in operation, suspend all l operations involving a reduction in boron concentration of l

the Reactor Coolant System and immediately initiate

! corrective action to return the required coolant loop to opration. -

C. Whenever the reactor is in Mode 4 or 5 the fo!!owing conditions shall be met: ,.g

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

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

8 Amendment No. 2[J3', M 79

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3:22 FIRE PROTECTION SYSTD3 Applicability This specification applies to the operational status of the plant fire protection and detection systems.

Obieetive To ensure the availability of *.he fire protection and detection systems. .

Specification A. Fire Suppression Water. Systems 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 gpm, with their discharge aligned *' to the -

fire suppression header.

b) Automatic initiation logic for each fire pump.

A.2 From and after the date that one fire pd=p is determined to be inoperable, restore the pump to operable status within 7 days or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2

,, within 30 days of the occurrence outlining the plans and 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 is determined to be inoperable kith the plant l in any operating mode: ,

a) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> establish a backup Fire Suppression Water System, '

( and notify the Regional Administrator of the event by telephone l with confirmation by telegraph, mailgram or facsimilie trans-mission no later than the first working day following the event.

Within 14 days following the event, prepare and submit a Special Report pursuant to Specification 6.9.2, outlining the actions taken, the cause of the malfunction and the plans and schedule for restoring the system to operable status; or l b) The plant shall be placed in at least Hot Standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

I 3-41 Amendment No. M g 79

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B. Carbon Dioxide Systems B.1 The following CO2 Systems shall be Operable with the indicated, connected "

minimum number of bottles of CO2 and available for service and having at least 90: '

of full charge weight, whenever the protected equipment in the area is required to be Operable:

a) Cable Vault (18) .

b) Primary Anr111ary Building Charcoal Filters (8)

B.2 From and after the time a CO2 system listed in B.1 is determined to be inoperable, within one hour establish a continuous fire vecch with backup fire suppression ' equipment for the unprotected equipment and/or area.

• B.3 Restore the system to Operable status within 14 days or prepare and submit a .Speciil Repor,c to the Commission pursuant to Specification 6.9.2 '.vichin ',

30 days of the occurrence outlining the cause of ,the inoperability and the plans for restoring the system ,

to Operable status.

! C. Halon 1301 System i

C.1 The Halon 1301 System for the svitchgear room shall be operable with at least (7) Halon bottles connected and available for service and each bottle shall be at least j2% 2 of full charge weight'.

C.2 From and af ter the time the Halon system listed in C.1 is determined to be inoperable within one hour establish a continuous fire vacch with backup fire suppression equipment for the unprotected equipment and/or area.

C.3 Restore the system to operable status within 14 days or prepare and submit a . Spec {fl. Report to the Coussission pursuant to Specification 6.9.2 within 30 days of the occurrence outlining the cause of the inoperability and,the plans for restoring the system to operable status. '.

D. Fire Water Stations

-D.1 The Fire Water Stations listed in Table 3.22-1 shall be Operable.

3 2 knendment No. 2f, 2g, p,(, 79

B. Strek Widt.Rrnge Soble ces Monitor B.1 One stack vide range noble gas monitor channel shall be

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

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

j b) The alarm setpoint 3,ess than or equal to the l 1

monitor reading coriesponding 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 Report to the Com=ission pursuant to Specification 6.9.2' within the next 10 days outlining:

the cause of the malfunction, the plans for restoring the channel to operable status, and any alternative methods for estimating stack release rates during the interim. ]

Basis s.

These specifications ensure the operability of'the high range .

containment radiation monitors and wide range stack noble gas monito rs. These monitors are required for post-accident assess-ments. 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 TMI Action Plan Requirements," November,1980.

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i 3-46 Amendment No.)E$I 79

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

E. ' Fire Detection Systems .

E.1 The minimum number of detecto'rs for each fire detection zone shewn in Table 3.22-2 shall be OPERABLE.

E.2 ACTION Whenever the number of OPERABLE detectors is less than the minimum number 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 watch patrol o

. . 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 contain:nent air temperature at least once per hour at the locations referenced by Specification 4.4 Containment Testing) .

,b . Restore the inoperable instrument (s) to OPERABLE

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status within 14 days, or, prepare and submit a Special Report to the Commission pursuant to

! Specification 6.9.2 within the next 30 days 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 (in'cluding cable penetration barriers, fire dodr's and fire dampers) that protect safety related areas shall be functional.

F.2 From and after 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 vecch 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) hour.

i 3 3 Amendment No. 2d, 28,M 79

G.2 From and af ter the time any of the spray and/or sprinkler systems listed in G.! is determined to be inoperable, within ooe hour, establish a continuous fire watch with backup fire suppression for those areas starred (*) in G.!; for other areas, establish a fire. patrol to inspect the applicable unprotected area at intervals of at ! cast once cach hour. .

G.3 Restore the inoperable system to operable status within 14 days cr prepare and submit a Sp cial Report to the Commission pursuant to Specification 6.9.2 within 30 days of the occurrence outlining the cause of the inoperability and plans for restoring the inoperable system to operable status.

H. Ft.AMM ABt.E LIQUIDS CONTROLS .

Flammable liquids in volumes greater than 1 p' int shall be restricted from the control room except under the following conditions:

1. . Written permission is obtained from the Supervising Control Operator or Shif t Supervisor, and

2. The flammable liquid is contained in' a suitable

• container not to exceed one quart in volume, and

3. A dedicgted fire watch is assigned to the activity. ,

• A suitab!c c-tainer is non-spillable and.has a fla,me arrestor in the nozzle.

Easis A. Fire Detection and Suppression Systems i

Fire suporession Systems The operability of the fire suppression systems ensures that adequate fire suppression capability is availab!c to confine and extinguish fires occurring in any portion of the facility where safety related equipment is located. The fire suppression system consists of the water systems, spray and/or sprinklers, CO2 Systems, Halon 1301 Systems, fire hose stations and hydrants. The capability of the fire suppression systems is adequate to minimize potential damage to saf ety related equipment and i's a major element in the f acility fire

! protection program.

3-44a Amendment No. g g ys, 79

3.23 Pmt Accident Instrumentntian Applicability This specification applies to spef:ific plant instrumentation required for post-accident assessments.

Obj ective To ensure the instrumentation will be operable if required.

Specification A. Containment High 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 k'ith one or more channel (s) inoperable, restore the inoperable channel (s) to operable status

• within 7 days, or else prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining: the cause of the malfunction, the plans for restoring the chantiel to operable

.. status, and any alternative methods for esti-mating containment dose rates during the interim.

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e 3-45 Amendment No. [ 79

l BASIS The Surveillance Requirements for inspection of steam generator tubes ensure that structural Integrity of this portion of the reactor

coolant pressure boundary w111 be maintained. . The program for i

inservice inspection of steam generator tubes is based on the following criteria.

a) Modification of Regulatory Guide 1.83, Revision 1. -

b) On previous Eddy Current Examinations results

! Inservice Inspection of steam generator tubing is essential in order to

~ maintain surveillance of the conditions of tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or laservice conditions that lead to corrosion, or excess leakage. Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of, any tube degradation so that corrective measures can be taken.

The plant is expected to be operated in a manner such that the -

secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tthes. i Specified chemistry treatment of the secondary coolant also limits the  ;

possibliity of wastage - type defects. If the secondary coolant j chemistry is not maintained within these limits, localized corrosion i may result in stress corrosion cracking. The extent gf cracking during plant operation would be limited by the limitation of steam generator tihe leakage Mi.;;;a the primary coolant system and the secondary j system imposed in Specification, Section 3.14, Primary System 1 Leakage. Operating plants have demonstrated that primary to l secondary leakage specified in Specification 3.14 can readily be l detected by radiation monitoring of steam generator blowdown. ,

I

~ If a defect should 1d+ in service, it should be found during scheduled inservice steam generator tube examinations. Plugging or sleeviry will be required for all tubes with imperfections equal to or hwdng the plugging limit of 30% of the tube nominal wall thickness. Tubes containing sleeves with imperfections e:+r Mg the plugging limit will be plugged. Steam generator tube inspections of operating plants have demonstrated the SM !Ity to reliably detect degradation that has penetrated 20% o" the original tube wall thickness. -

Th..eu. the results of any steam generator tibing inservice  ;

, -inspection fall into Category C-3, these results will be promptly l reported to the Commission pursuant to 1D CFR 50.72(b)(S) prior to resumption of plant operation.

l l

4-21e I Amendment No.)0', 79

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

) TABLE 4.10.1-2

~

STEAM GENERATOR TUDE INSPECTION i ist SAMPLE INSPECTION 2nd SAMPLE INSPECTION 3rd SAMPLE INSPECTION i

1 Sample Size Result Action Required Result Action Required Result Action Required A minimum of ~ C-! None N/A N/A 5 Tubes per N/A N/A. l S.G.

I .

C-2 Repair defective tubes C-1 None and inspect additional N/A N/A Repair C-I None 25 tubes in this S.G.* C-2 defective tubes C-2 Repair and inspect defective tubes

• additional 45 tubes ,. C-3 Perform action for in this S.G.* C-3 result of !!rst sample 1

' C-3 Perform action for N/A N/A C-3 result of first sample j

C-3 '

Inspect all . All other tubes in S.G.s are None this S. G., repinir C-I N/A N/A i i

defective tubes and Some S.G.s Perform action for N/A inspect 25 tubes in C-2 but no N/A '

C-2 result of second each other 3.G.* additional sample S.G. are

' Prompt notification C-3 to NRC pursuant l

to 10.CFR 50.72(b) Additional Inspect all: '

(2) 5.G. Is C-3 tubesin each S.G. and repair defective tubes.' '

Prompt notification N/A N/A .

to NRC pursuant

to 10 CFR 50.72(b)

(2) 5:12 %

Where n is the number of steam generators inspected during an inspection.

• Repair sleeves of be shall defective plugged. tubes shall be limited to plugging with the exception of those tubes which may be sleeved. Tubes wit 4-21s Amendment' No. Jhd8, 79 i

CONNECTICUT YANKEE AiOMIC POWER COMPANY OFTSITE ORGANIZATION CYAPCO Chairman NUSCO Chairman and Chief Executive Officer

. CYPACO President NUSCO President and Chief Operating Officer CYAPC0 Executive Vice President

. and Chief Operating Officer NUSCO Executive Vice President Engineering and Operations CYAPCO Senior Vice President

. NUSCO Senior Vice President i

.. - Nuclear Engineering and Operations I l Nuclear Review Northeast Utilities l

Board Service Company (NUSCO)*'

. . CYAPCO Vice President

1. NUSCO Vice President Nuclear Operations Nuclear Operations Connecticut Yankee Station

. Staff Superintendent - Onsite l

• Provides Operating and Technical Suppor,t by Contractual Arrangement

! Figure 6.2-1 i

6-2 Amendment No. Ik

ADMINISTRATIVE C0!;TROLS

/ 1 6.5.2 NUCl. EAR REVIEk' BOARD (NRB) n1NCTION

• 6.5.2.1 The Nuclear Review Board shall function to provide independent review and audit of designated activities in the creas of: 3

a. nuclear pover plant operations

b. nuclear engineering

+ e;

c. chemistry and radiochemistry **

d. metallurgy .

e. nondestructive testing

f. instrumentation and control .

g. radiological safety

h. mechanical and electrical enginedring

i. administration -

j. quality assurance practices

{

i

}

j l

I l

6-8 ' Amendment No. 79

AD.m HISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The NRS shall consist of no less than seve'n. nor more than eleven members including the Chairman and the Station Superintendent.

The Chairman and members of the NRB shall be ap;Iointed in writing by the Senior Vice President - Nuclear I..gineering and Operations, and shall have an academic degree in engineering or physical science field or equivalent ex-perience.

Technical ~ experience in the areas specified in Section 6.5.2.1 may be substituted on a one-for-one basis touards the acadenic degree requirement. (Four years of technical experience being equivalent to a four-year academic degree.) In addition, they shall have a minimum of five years technical experience, of which a minimum of three years shall be in their respective field of expertise /

Total academic and technical experience must total a 3 minimum of nine years CONSULTANTS . -

6.5.2.3 Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to, the NRB. l MEETING FREQUENCY 6.5.2.4 The' NRB shall meet at least once per six months.

t .

l QUORLM

, 6.5.2.5 The minimum quorum of thi N 4 tr, a ssary for the performance of

~

the NRB revieu and audit ionctions of these Technical Specifications l

• shall consist of the Chaircan or his designated alternate and,at 1 east four (4) NRB members. No more than a minority of the quorum shall have line respotsibility for operation of the facility.

6-9 Amendment No.

79 M.

I ADMINISTR ATIVE CONTROI.S REVIEW 6.5.2.6 The NRB shall review:

a.

The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.

b.

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 30.59,10 CFR.

c.

Proposed tests or experiments which involve an 6nreviewed safety question as defined in Section 50.59,10 CFR.

d. .

Proposed changed in Technical Specifications or licenses, e.

Violations of applicable statutes, codes, - regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nucle'ar safety significance.

f.

Significant ope: rating abnormalities or deviations from normal and

. expected pericrmance of plant equipment that affect nuclear safety.

1

.. g. All reportable, events. .

h. Indica. ions of a signatiiant unanticipated deficiency, affecting nuclear safety, in soma ' aspect of designf or operation of safety related structures, systems or components.

i. Reports and mechng notes of the PORC.

I l

6-10 Amendment ?!o. 79.

I t

i ADMINISTRATIVE COhTROI.S

_ AUDITS 6.5.2.7 Audits of facility activities shall be performed under the  !

cognizance of the NRB. These audits shall encompass:

l

a. i The conformance of unit operation to provisions .!

contained within the Technical Specifications and .

applicable license conditions at least once per 12 months.

l

b. The performance, training and qualifications sf the facility staff at least once per 12 months.

c.

The results of actions taken to correct deficiencies l

• occurring in facility equipment ' structures, systems or method of operation that affect nuclear safety at least once per six months.

d.

The performance of activities required by the Quality l Assurance Program to meet the criteria of Appendix "B",

10 CFR 50, at least once per 24 months.

l

e. The Emergency Plan and implementing procedures at least once per 24 months.

.. V

f. The Security Plan and implementing procedures at least once per 24 months. -

g. Any other area of facility operation' considered appropriate by the NRB or the Senior.Vice President-Nuclear Engineering

, and Operations. '

h. The Fire Protection Program,and implementing procedures

• at least onc(.per 24 months.

l

1. An inspection and audit of th'e Fire Protection and loss '

} '

prevention program shall be performed at least once per 12 months by an outside firm experienced in fire proccction ,

and loss prevention.

AUTHORITY 6.5.2.8 The NRS shall. report to and advise the Senior Vice President-Nuc1 car Engineering and Operations on those areas of responsibility specified in Section 6.5.2.6 and 6.5.2.7. Mee ting minutes may be used for this purpose. l 6-11 Amendment No. I9

ADMINISTRATIVE CONTROLS *

~

RECORDS

-6.5.29 Records of NRB activities shall be prepared, approved and [fistributed as indicated below: l

a. Minutes of each NRB meeting shall be prepared, approved and 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.

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

l

c. Audit reports encompassed by Section 6.5.2.7 above, shall be

. t,

[

forwarded to the Senior Vice President-Nuclear Engineering and .

Operations and to the mansgement positions responsible for the areas audited within 30 days after completion of the audit.

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6-12 Amendment No. g )0$

79:

9 ADMINISTR ATIVE CONTROLS 6.6 4

REPORTABLE EVENT ACTION

, 6.6.I The fo!!owing actions shall be taken for Reportable Events:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Section 50.73 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 Theted.

viola following actions shall be taken in the e. vent a Safety Limit i

~

a.

The unit shall be placed in at 'least HOT STANDBY within one hour .

b.

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

' Nuclear Operations and the NRB shall'be dotifie .

c.

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

.. applicable circumstances preceding the violation, (2) effects of thes 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 within 14 days ofthe Commission, theNRB and the Vice President-Nuclear Operations violation.*

6.3 PR OCEDURES 6.S.!

4 Written' procedures and', administrative policies shall be established, implemented and maintained that meet or exdeed the requirements an recommendations of Section 3.1 and 3.3 of ANSI N13.7-1976 an 6.S.2 and 6.5.3 below. Appendix "A" of USAEC Regulatory Guide 1.

t for implementation of tl}c Facility Fire Protection Program, Pro 6.I.2 i

thereto, shall be reviewed by the PORC a on and app 4

1 Superiniendent each document. prior to implementation and periodically as set forth in 6.-13 Amendment No. M M 9

6.9 REPORTING REOUIREMENTS in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted

to the regional administrator of the appropriate Regional Office unless otherwise noted. [

6.9.1 Routine Reports '

a.

Startuo Report - A summary report of plant startup and 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 manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the I nuclear, thermal, or hydraulic performance of the plant.

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

Any corrective actions that were required to obtain satisfactory operation sha!! be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

. ~

Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or, commencement of commercial' power operation, or '(3) 9 months following initial criticality, whichever is earliest., if the Startup l

Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation),. supplementary reports shall be submitted at least every three months until $11 three events have been comple ted. '

b.

Steam Generator Tube insoection - The complete results of the sicarn generator tube inservice inspcCljon shall be reported within ninety days after completion of the inspection. This report sha!! include:

1) number and extent of tubes inspected.

2)

?.ocation and percent of u all thickness penetration for each indication of an imperfection.

3) Identification of tubes plugged.

i 6-15 Amendment flo. k 79

-+-

l

~

c. Occuoational Exposure Report and shall cover the previous calendar ye be submitted prior to March criticality.  ! of the year following initial Thisnumber the annualofreport shall station, include a tabulation on an annual basi utility contractors) receiving exposures, greater than 100 mrem functions, te e.g., reactor operations and sur inspection, routine maintenance, special maintenance (describe maintenance), waste processing and refueling. The dose assignment to various duty functions may be.est.imated based on pocket dosimeter, TLD, or film badge -4ncasur' ements.

.,. Small exposures totalling not be accounted for.

less than 20% of the individual total does need In the aggregate,'at least 30% of the total whole body specific dosefunctions.

major work receive from external sources shall be assigned d.

Monthly Operating Report - Routine reports of operating statistics

• and shutdown experience shall be submitted on a monthly basis to the Director, . Office .of Management Information Control, U. 5. Nuclear Regulatory Commission, Washington, D. C.and 20535, with a copy to the appropriate Regional Office, to be

,, ... pos'tmarked no later than the fitteenth of each month following the calendar month covered by the report.

The monthly report shall include a narrative summary of operating experience during the rep' ort period relatipg to safe operation of the facility, including safety-related maintenance.

c. ,

Reports required as per 10 CFR 50.39b.

a O

6-16 Amendment No. 79

FOOTNOTES j

1. A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

J

2. The term " forced reduction in power" is normally defined in the electric i power industry as the occurrence of a component failure or other condition )

which requires that the load on the unit be reduced for corrective action  ;

immediately or up to and including the very next weekend. Note that i routine preventive maintenance, surveillance and calibration activities requiring power red.uctions are not covered by this section.

~

3. The term " forced outage" is normally defined in the electric power industry as the occurrence of a component failure or other condition which requires that the unit be removed from service for , corrective l

action.immediately or up to and including the very next weekend.

4. This tabulation supplements' the requirements of $20.407 of 10 CFR Part 20.

e

(

)

l 6-17 Amendment No. 79

- , . -- + , . - - .,

---

,n.--, -

o .

. ADMINISTRATIVE CONTROLS -

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office within the time period specified for '

each report. These reports shall be submitted covering the activitics identified below pursuant to the requirements of the applicable reference specification:

a. Inservice Inspection results. Specifications (4.10) and (4.12).

b. Primary Containment Leak Rate Results Specification (4.4).

c. Reactor Vessel Haterial Surveillance Specimen Examination,

- 3, . Specification (4.10). " '

v:- .

d. Steam penerator Tube Re' port

• 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. -

e. Post-Accident Instrumentation Operability Specification (3.23 A and 8)

f. Fire Protectfon Systems Operability, Specification (3.22) 6.10 ~ *RECORD RETENTION

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

a. Records and logs o,f facility operation covering the time interval at each power level.

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related tp nuclear safety.

c. All reportable . events.

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

4 4

6-18 Amendment No. JK f6', 79 l

_. . - . _ -- - . _ _ __. _ _ _ -- ._ - .= __- - , _ _ _ _ - __

NMIllISTRATIVE CDTRO'.S

e. Records of reactor tests and experiments.

' f. Records of changes made to Operating Procedures,

s. Records of radioactive shipments.

h.

Records of seaied socice 1eak tists and results.

i.

Records of ann,ual physical inventory of all source material of record.

J. Radiation z$d contamint.: ion surveys.

• 6.10.2 Tne following Facility operating records shall be retained for the durae\ ion of the 1.icense: -

a.

• Record,and drawing changes reflecting fa:ility design codifi-

• cations cade to syste::ts and couiomen: described in the Facili:y Description and, Safe:y Analysis Report.

h.

Records of asser.biy burnup new and irradiated fuel inventory, histories.

fuel transfers and

' .c .

R::c::s of facility radiatica and contaminz:ica surveys ,

i

d. Recobs cf radiation exposure for all individuals en:Erinc radia: ion control areas. -

~

e.

Records of gaseous and liquid ~ radioactive material relefsed to the

. environs.  :

/

f. ,, Records cf transient or operaticnal cycles for those. facility

'co=ponents designed for a limited nu=5er of :ransients or cycles.

S.

Records plant of training an'd qualification for current members of the staff, h.

Records ofspecifications.

Technical in-service inspections perfomed ' pursuant to these i., Records P.anual .

of*0uality Assurance activities required by the QA J.

Records of reviews perfomed for changes made to procedures or e:;uipment or reviews of tests and experiments pursuan: o 10 CR 50.50

k. Records of cretings of the PO?.c and the ,;;-a, -

j 1.

1 Records for Envirnnment51 Qdliffration.

1 e

6-19 Amendment fio. [79

~

i

, AD111NISTRATIYC C0ffTR01.5 -

9 -

6.11 RADIATIO!! PROTECTIO!! PP.0GRA'i Frocedures 'for personnel radiation protection shall be pn:sfred consistent with the require:acnts of 10 CFR Part 20 and shall be approved, ciaintained exposure. and adhered to for all operations ir.volving perst,nnel radiatior, 6.12 SUPERSEDED BY 10 CFR 20.103(c) AND (f) ON DECEMBER 28, 1977 6.13 HICH RADIATION AREA

~

, 6.13.1 ,, ,

s In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c) (2), each high radiation area in *which the intensity of r,adiation is 1000 arem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance theretoshall be' controlled by requiring issuance of a Radiation Exposure Authorization *. An individual or group of individuals permitted to enter such areas shall be provided with one or more of the following: .

a'. A radiation monitoring device which continuously indicates the

'e

. radiation dose rate in the area. .

b .' A radiation m'onitoring device which continuously integrates the 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 raye level in the area have been established and personnel have been made knowledgable of them. ~

c. A health physics qualified individual (i.e. qualified in ~ radiation '

protection procedures) whh a radiation dose rate monitoring device who is responsible for pro'viding positive control over the .

! activities within the area and who will perfor,m periodic radiation survei.11ance at the frequency specified in the REA. The surveillance frequency will be established by the Health Physics Supervisor.

~

The above procedure shall also apply to cach high r&diati-on 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 be maintained under the ad=inist rative control of the shift supervisor on duty.

• Health Physics personnel shall be exempt during the ; erforr.ance of their assicr.cd radiarimfrom the REA issuance requirement rre:utfen duties, previdinr. they are following plant radiatten prot.' : ten procedures for entry

,i

,nto high radiation areas.

.7 O 6-20 A=nd:nent tio. [79 l

~

d

. l ADMINISTRATIVE CONTROLS

• 6.14 (Deleted) 6.15 SYSTDiS INTECRITY The licensee shall imp 1ement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accid.ent to as lov as practical levels.

following: This program shall include the

1. Provisions establishing preventive maintenance and periodic visual inspection require:sents, and

2. Integrated leak test require:nents for each system at a frequency not to exceed refueling cycle intervals. -

.. 6.16 IODINE HONITORING .

~

The licensee shall implement a progran which vill ensure the capability to accurately determine the airborne concentration in vital areas under accident conditions. This program shall include the following:

1. Training of personnel. -

2. Procedures for monitoring, and 3.

Provisions for maintenance of sampling and analysis equi;::ent.

e D

E O

O 6 21 Amenoment tto. f[. [

79

~

e

• ADMINISTRATIVE CONTROLS 6.17 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE

_ CALCULATION M ANUAL(REMODCM) ~

Section I, Radiological Effluents Monitoring Manual, shall outline the

- sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to Individuals in those exposure pathways and for those radionuclides released as a result of station operation. It shall also specify operating guidelines for radioactive waste treatment systems and report content.

Changes to Section I shall be submitted to the Commission for approval prior to implementation.

Section II, the Offsite Dose Calculation Manual (ODCM), shall describe the methodology and parameters to be used in thecalculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in i these technical specifications. Changes to Section II need not be i

submitted to the Commission for approval prior to implementation, but shall be included in the next Semi-Annual Radioactive Effluent Release Report.

• 6.18 R ADIOACTIVE WASTE TREATMENT SYSTEMS Procedures for liquid and gaseous radioactive effluent discharges from the Unit shall be prepared, approved, maintained and adhered to for all operations involving offsite reIcases of radioactive effluents. These procedures shall specify the use of appropriate waste treatment systems utilizing the guidance provided in the REMODCM. ,

The solid radioactive waste treatment system shall be operated in accordance with the Process Control Program to process wet radioactive

• wastes to meet shipping and burial ground requirements.

G-22 knendment I40.Y' I9

. . . . ~

R ADICACTIVE EFFLUENTS -

DOSE, LIQUIDS , .

, LIMITINd CONDITION FOR OPERATION 7.1.12 The dose or dose commitment to any MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the site shall be limited: .

a. During any calendar quarter to less than or equal to 1.5 mrem to th4 total body and to less than or equal to 3 merm to any organ, and

b. During any calendar year to less than or eq'ual to 3 mrem to the total body and to less than or equal to 10 merm to any organ.

, APPLICABILITY: At a!! times. ,

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2.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 rnrem to the total body and 10 mrem to any organ.

s' SURVEILt ANCE REQUIREMENTS ,

3.1.1 J.4 Dose Calculations. Cumulative dose contributions from liquid etfluents shall be determined in accordance with Section 11 of the REMODCM. '

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

J 7/8 l-2 Amendment No. 79

R ADIO ACTIVE EFFLUENTS

• DOSE, NOBLE C ASES -

LIMITirQG CONDITION FOR OPERATION . ,

7.122 The air dose offsite due to noble gases released in gaseous effluents sha!! 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 a!! times. -

~

ACRON:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies me cadse(s) for exceeding me limit (s)'and -

j defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous efffuents during the remainder of the current calendar quarter and during me remainder of the calendar i

' " 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 8.1 J.2.1- Dose Calculations. Cuchulative dose contrilgutions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with Section 11 of the REMODCM once every 31 dys.

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

i 7/81-4 Amendment No , 79

_R ADIOACTIVE' EFFi.UENTS

• DOSE,'R ADIONUCLIDES, RADIOACTIVE M ATERIAL IN PARTICULAT R ADIONUCLIOES OTHER TH AN NOBLE GASES

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

a.

During any calendar quarter tc, less than or equal to 7.3 mrem to any organ;

. b.

, During any calendar year to less than or equal to 15 mrem to any

. organ.

APPLICABILITY: At all times. .

ACTION:'

a. With the' calculated dose from ttje release of radionuclides, radioactive materials in particulate form, or radionuclides other than noble gases in Easeous effluents exceeding any of the above limits, prepare and

• submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report whictiidentifies the cause(s) for exceeding the limit 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.

~

SURVE!! LANCE REQUIREMENTS

• 8.1.2.3.1 Dose Calcufotions Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with Section II of the R,EMODCM 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.

7/8 l-3 Amendment.tio. 79

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

T

. RADIOACTIVE EFFLUENTS

\

7/8.1.3 TOTAL DOSE '

LIMIThG CONDITION FOR OPERATION  !

7.1.3- '

The dose or dose commitment to a MEMBER OF THE PUBLIC from the site is limited to less than or equ' al 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 a!! times.

ACDON: - -

a.

• With the calculated dose from the release of ra'd ioactive materials in b.*

liquid or gaseous effluents exceeding twice the liinits of Specification 7.1.12.,7.12.2., or 7.12.3., prepart and submit a Special Report to the Commission pursuant to Specification 6.9.2 and limit the -

l s'ubsequent releases such that the dose or dose commitment to any MEMBER OF THE PUBLIC 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 shall include a request for,a variance in accordance with the pro' visions of 40CFR190. Submittal of the report is considered a tirr-ly request, and a variance Is granted until staf f action on the request 1. umplete.

SURVEILLANCE REQUIREMENTS , 3.1.3 Dose Calculations tumulative dose contributions from liquid and gaseous cffluents and directeadiation from the site shall be determined in Specifications 3.1.12.1,8.1JJ.! and 8.1.2.3.1 and In accordance with Section !!of the REMODCM once per 31 days.

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