ML20069N260

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Proposed Tech Spec Section 6, Administrative Controls
ML20069N260
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 06/13/1994
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20069N242 List:
References
NUDOCS 9406220311
Download: ML20069N260 (36)
v • d • e


Text

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ADMINISTRATIVE CONTROLS i

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SECTION PAGE 1

4 6.1 RESPONSIBILITY................................................ 6-1 3

i 6.2 ORGANIZATION.................................................. 6-1 a

I FIGURE 6.2-1 (THIS FIGURE NOT USED)............................... 6-3 l FIGURE 6.2-2 (THIS FIGURE NOT USED)............................... 6-4 l TABLE 6.2-1 MINIpRM SHIFT CREW COMPOSITION. . . . . . . . . . . . . . . . . . . . . . . . 6-5 FAciaw

6. 3 iMR- STAFF 00ALIFICATIONS. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6  ;

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1 6.4 TRAINING...................................................... 6-6 6.5 REVIEW INVESTIGATION AIS AUDIT................................ 6-6 1 1

6.5.1 0FFSITE..................................................... 6-6 Offsite Review and Investigative Function................... 6-6 l Station Audit Function...................................... 6-8 Authority................................................... 6-9 Records..................................................... 6-10 Procedures.................................................. 6-10 Personne1................................................... 6-10 6.5.2 0NSITE....................................................... 6-12 Onsite Review and Investigative Functions................... 6-12 Responsibility.............................................. 6-12 Authority................................................... 6-13 Records..................................................... 6-14 Procedures.................................................. 6-14 Personne1................................................... 6-14 6.6 REPORTABLE EVENT ACTI0N....................................... 6-15 BYRON - UNITS 1 & 2 XIX AMENDMENT ND. pi 1 9406220311 940613 PDR ADOCK 05000454 P PDR

t ADMINISTRATIVE CONTROLS SECTION PAGE 6.7 SAFETY LIMIT VIOLATION........................................ 6-15 6.8 PROCEDURES AND PR0 GRAMS....................................... 6-16 ,

. )

6.9 REPORTING REQUIREMENTS........................................ 6-20 f

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6.9.1 ROUTINE REP 0RTS............................................. 6-20 Startup Report....................:......................... /

6-20 Annual Reports..............................................

6-20 Annual Radiological Environmental Operating Report.......... (

6-22 l M nual Radioactive Effluent Release Report.............. 6-22 Monthly Operating Report....................................  !

6-22 Operating Limits Report.....................................

6-22 Criticality Analysis of Byron and Braidwood Station Fuel Storage Racks. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-23 /

6.9.2 SPECIAL REP 0RTS............................................. 6-23

/

6.10 RECORD RETENTION................... ......................... 6-23' k 6.11 RADIATION PROTECTION PR0 GRAM................................. 6-24 i <

6.12 HIGH RADIATION AREA.......................................... 6-25 i l

6.13 PROCESS CONTROL PROGRAM (PCP)................................ 6-26 6.14 0FFSITE D0SE CALCULATION MANUAL (00CM)....................... 6-26 4

BYRON - UNITS 1 & 2 XX AMENDMENTNo.M

DEFINITIONS I

0FFSITE DOSE CALCULATION MANUAL 1.18 The 0FFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology '

and parameters used in the calculation of offsite doses resulting from radio-

- active gaseous and liquid effluents, in the calculation of gaseous and liquid I effluent monitoring Alam/ Trip Setpoints, and in the conduct of the Environ-mental Radiological Monitoring P am. }

Radioactive Effluent Controls and The 00CM shall also contain (1) the iological Envirsnmental Monitoring Progress f required by Sections 6.8.4e and f, and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and )

-Sem&annuak Radioactive Effluent Release Reports required by Specifications 6.9.1.6 and 6.9.1.7. .

( s OPERABLE - OPERABILITY 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATING LIMITS REPORT 1.19.a The OPERATING LIMITS REPORT is the unit-specific document that provides operating limits for the current operating reload cycle. These cycle-specific p s

operating limits Specification shall be detemined for each reload cycle in accordance with 6.9.1.9. Plant operation within these operating limits is addressed in individual specifications.

OPERATIONAL MDDE - MDOE 1.20 An OPERATIONAL MDDE (i.e., MDDE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation: (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission, ,

j

' l PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE B00NDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall. **

BYRON - UNITS 1 & 2 1-4 AMENDMENT NO. M

. . - = . _ - . - - . - . . _ .... . - . -- - - - - = .. . - . - - -

l 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.1 Deleted 3.11.1.2 , Deleted 3.11,.1.3 Deleted  !

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3.11.1.4 The . quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in tny outside tanks shall be limited to the following:

a. Primary Water Storage Tank 5 2000 Curies, and
b. Outside Temporary Tank  !

5 10 Curies.

APPLICABILITY: At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> raduce the tank contents to within the limit, and describe the events leading to this condition Report, pursuantin the to next 4emiannual Specification Radioactive Effluent Release 6.9.1.7.

b. The provisions of Specification 3.0.3 are not' applicable. R l

i SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

BYRON - UNITS 1 & 2 3/4 11-1 AMENDMENT NO. h

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RADI0 ACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 5x104 Curies of noble gases (considered as Re-133 equivalent).

~

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the tank contents to within the limit, and describe the events leading to this condition in the next !:rf:- :! Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
b. The provisions of Specification 3.0.3 are not applicable.

P SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when radioactive materials are being added to the tank.

BYRON - UNITS 1 & 2 3/4 11-3 AMENDMENT NO. h

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager, Byron Station, shall be responsible for overall 4

Q ,;),'4 9 - mie, operation and shall delegate in writing the succession to this respon-

sibility during his absence.

j 6.1. 2 The Shift Engineer (:r during hi; :tnan frc,;. th: natr:1 rna; ;

daignt
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dirf.tding kt. Codrol reeve to*%veawd fW CIion MMS kt h o Mrg{iong 6.2 ORGANIZATION

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! 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS ,

1 Smci\ih )

l Onsite and offsite organizations shall be established for w e operation and

corporate management, respectively. The onsite and offsite organizations I

shall include the positions for activities affecting the safety of the nuclear

power plant.

! a. Lines of authority, responsibility, and communication shall be

' established and defined for the highest management levels through intermediate levels to and including all operating organization 4

positions. These relationships shall be documented and updated, as

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appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and  ;

i job descriptions for key personnel positions, or in equivalent forms t

of documentation. These requirements shall be documented in the I i

Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activities; Section 6

' Interdepartmental Relationships. }

" {o6cility )

b. The Station Manager shall be responsible for overall tm% safe f operation and shall have control over those onsite activities j j necessary for safe operation and maintenance of the plant.

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c. The Senior Vice President-Nuclear Operations shall have corporate

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responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in j

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' operating, maintaining, and providing technical support to the plant to ensure nuclear safety. 1 i

i d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the 4

appropriate onsite manager; however, they shall have sufficient

, organizational treedom to ensure their independence from operating j j pressures.

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BYRON - UNITS 1 & 2 6-1 AMEN 0 MENT NO. M er s- - , - -= - -- -

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- ADMINISTRATIVE CONTROLS f

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6.2.2 SNtf STAFF The g . staff shall be subject to the following: I

a. Each on duty shift shall be composed of at least the minimum shift
crew composition shown n Table 6.2-1; and '

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b. AtleastonelicenseddpeYaEorshallbeinthecontrolroomwhen fuel is in the reactor. In addition, while the unit is in MODE 1,
2, 3, or 4, at least one licensed Senior g0perator shall be in the j control room; Reader
c. ' A Radiation Protection Technician,* qualified in radiation protection j

, procedures, shall be on site when fuel is in the reactor; i

Raukt she

d. AllCOREALTERATIONSshal'Jbeobservedanddirectly ervised by i

either a licensed Senior 4perator or licensed Senio parator-Limited to Fuel Handling who has no other concurrent responsibilities during j this operation; .

! e. Administrativeproceduresshall]bedevelopedandimplementedto j limit the workin j functions; e.g. ,glicensed hours ofSenior im4f staffrators, who perform licensedsafety-related erators, health physics personnel, equipmen operators, and key maintenance j personnel. hade Ace.W l The amount of overtime worked by Istaff members performing safety-related functions shall be limited in accordance with the

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4 NRC Policy Statement on working hours (Generic Letter No. 82-12); l

f. The Assis' tant Superintendent Operating shall hold a Senior Reactor Operator License. 4

,5 i

6.2.3 ONSITE NUCLEAR SAFETY GROUP (ONSG)

! FUNCTION

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- 6.2.3.1 The ONSG serves as an independent safety engineering group and shall function to examine plant operating characteristics, NRC issuances, industry l

advisories, REPORTABLE EVENTS and other sources of plant design and. operating experience information, including plants of similar design, which may indicate

! areas for improving plant safety. The ONSG shall make detailed recommendations i

' for revised procedures, equipment modifications, maintenance activities, opera-j tions activities or other means of improving plant safety to the Safety {

Assessment Manager, and the Station Manager, Byron Station.

1

, COMPOSITION 6.2.3.2 The ONSG shall be comp'osed of at least three, dedicated, full-time

} engineers located on site.

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  • The Radiation Protection Technician may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected )

absence provided immediate action is taken to fill the required positions.

BYRON - UNITS 1 & 2 6-2
- AMENDMENT NO. Q

ADMINISTRATIVE CONTROLS 6.2.3 ONSITE NUCLEAR SAFETY GROUP (ONSG) (Continued)

RESPONSIBILITIES 6.2.3.3 The ONSG shall be responsible for maintaining surveillance of plant activities to provide independent verification

  • that these activities are performed correctly and that human errors are reduced as much as practical.

RECORDS 6.2.3.4' Records of activities performed by the ONSG shall be prepared, main-ta.ined, and forwarded each calendar month to the Safety Assessment Manager, "

and the Station Manager, Byron Station. 3 a ~

6.2.4 SHIFT TECHNICAL ADVISOR

.d TAdvisor he ' ^..^.,'. ,,,s.. . ".. . .'. . ._m___ '. ". . ."_.

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6p'p :: d't'::: th: cC"" Or :th:r :: data "T.^. shall providente_chnical support to the p an ift 'g:ri.7 in the areas of thermal hydraulics, reactor engineering and udvho ,_  ;

analysis with regard to the safe operation of the un&t. f=J).1.

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BYRON - UNITS 1 & 2 6-2a a

AMENDMENT NO. bl 6

l , -

TA8LE 6.2-1 MINIMUM SHIFT CREW COMPOSITION POSkON NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION [

\ BOTH UNITS IN DE 1, 2, 3, BOTH UNITS IN MODE 5 OR 6 ONE UNIT IN M00E 1, 2, 3 OR AND i OR 4 OR DEFUELED ONE UNIT IN MODE 5.0R 6 , DEFUELEE l J SE k 1 1 /

1\ None" 1 /

SF

. R0 38\ 2

[ l A0- 3

\ 3 /3 STA or \ / 1 SCRE 1 k None /

SE - Shift Superviso (Shift Engineer) ith a Senior Operator ,

license  !

SF -

Shift Foreman with Senior 0 retor license R0 -

Individual with an rator iconse AD - Auxiliary Operator . .

STA -

Shift Technical Advisor +%a(M SCRE - Station Control Room g er with a Senior Operator Licens b~

j The Shift Crew Composition may be ne less n the minimum requirements of l Table 6.2-1 for a period of ti not to excee 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate I unexpected absence of on-duty hift crew membe provided immediate action is taken to restore the Shift ew Composition to u hin the minimum requirements of Table 6.2-1. This pro sion does not permit an shift crew position to be unmanned upon shift cha e due to an oncoming shift rewman being late or absent.

During any absence o the Shift Supervisor from the con I room while the Unit is in MODE 1, 2, 3 r 4, an individual with a valid Seni Operator license shall be designa d to assume the control room command fu ion. During any absence of the hift Supervisor from the control room while Unit is in l MODE 5 or 6, n individual with a valid Operator license shal e designated to assume the ontrol room command function. ,

  1. At I t one of the required individuals must be assigned to the esignated pos ion for each unit.

NA least one licensed Senior Operator or licensed Senior Operator L ited to uel Handling must be present during Core Alterations on either unit, has no other concurrent responsibilities.

E. EE lok Asul "A" BYRON - UNITS 1 & 2 6-5 AMENDMENT NO. 41

INSERT "A" TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION (a) (f)

POSITION (D) MINIMUM CREW NUMBER ONE UNIT IN MODE 1, 2, 3, OR 4, AND ONE UNIT IN EACH UNIT IN MODE MODE 5, 6, OR EACH UNIT IN MODE 1, 2, 3, OR 4 DEFUELED 5, 6, OR DEFUELED SE 1 1 1 SRO 1 1 None (e)

RoldI 3 3 2 AO (d) 3 3 3 STA(c) 1 1 None (a) The shift crew composition may be one less than the minimum requirements of Table 6.2-1 for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to accommodate unexpected absence of on-duty shift crew members, provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shif t crew position to be unmanned upon shift change due to an oncoming shift crew member being late or absent.

(b) Table Notation:

SE - Shift Engineer with a Senior Reactor Operator license SRO - Individual with a Senior Reactor Operator license RO - Individual with a Reactor Operator license or a Senior Reactor Operator license AO - Auxiliary Operator STA - Shift Technical Advisor (c) The STA position may be filled by any individual who meets the Commission Policy Statement on Engineering Expertise on Shift. 4 (d) At least one of the required individuals must be assigned to the  ;

designated position for each unit.

]

(e) At least one licensed Senior Reactor Operator or licensed Senior  !

Reactor Operator Limited to Fuel Handling who has no other 4 concurrent responsibilities must be present during CORE ALTERATIONS l on either unit.

(f) With either Unit in MODE 1, 2, 3, or 4, an individual with a Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. With both units in MODE 5, 6, or defueled, an individual with a SRO license or Reactor Operator license shall be designated to assume the control room command function.

l BYRON - UNITS 1 & 2 6-5 AMENDMENT NO.

l

ADMINISTRATIVE CONTROLS TACMtY 6.3 SNtf STAFF QUALIFICATIONS ,4,,in ZeM 6.3.1 Each member of the uMdstaff hall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971, except f he Health Physics 4:7;i::: :: '_:: alepartmed,

,tett, 7t,y;t:i:t, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, for a Radiation Protection Manager. y o

6.4 TRAINING 6.4.1 A retraining and replacement training program for the fud.h amM staff shall be maintained under the direction of the Product < on Training Department and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /

ANS 3.1-1978, and shall include familiarization with relevant industry opera-  :;

tional experience from the program managed by Quality Programs and Assessment. '

6.5 REVIEW INVESTIGATION AND AUDIT The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below.

OFFSITE 6.5.1 The Superintendent of the Offsite Review and Investigative Function shall be appointed by the Manager of Quality Assurance / Nuclear Safety (QA/NS) responsible for nuclear activities. The corporate audit function shall be the responsibility of the Manager of QA/NS and shall be independent of operations.

The knager of QA/NS reports directly to the Chief Executive Officer and has use responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety. Policy is promulgated through a central policy committee directed by the Manager of QA/NS. The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out,

a. Offsite Review and Investigative Function The Superintendent of the Offsite Review and Investigative Function shall: (1) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (2) select each participant for this function, (3) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) independently review and approve the findings and recommendations developed by personnel performing the review BYRON - UNITS 1 & 2 6-6 AMENDMENT N0. M 9

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) f.

Written records of reviews performed in accordance with this specification i shall be prepared and maintained in accordance with Specification 6.10.

g. <

Editorial and Typographical changes shall be made in accordance with station procedures. d 6.8.3 made provided:Temporary changes to procedures of Specifica#pn 1 6.8.1 above, may be

a. The intent of the original procedure is not altered; b.

The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the Unit affected; and , be.ck,,

c.

The change is 6.8.2 documented, reviewed and approved in accordance with Specification within 14 days of implementation. )

/

6.8.4 The following programs shall be established, implemented, and maintained:

a.

Reactor Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the recirculation portion of the Containment Spray i i

System, and RHR System. Safety Injection System, Chemical and Volume Control System, The program shall include the following:

1)

Preventive and maintenance and . periodic visual inspection requiremen'ts, l

2)

Integreated cycle leakortest intervals requirements for each system at refueling less.

b. In-Plant Radiation Monitorina A program which will ensure the capability to accurately detemine the airborne iodine 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 equipasnt,
c. Secondary Water Chemistry A program for monitorirg of secondary we,ter chemistry to inhibit steam generator tube degradation. This program shall include: ,
1) Identification of a sampling schedule for the critical variables and control points for these variables, BYRON - UNITS 1 & 2 6-17 AMENDMENT N0. M

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS (Continued)

ANNUAL RADIOLOGICAL ENVIR0fMENTAL OPERATING REPORT

  • 6.9.1.6 The Annual Radiological Environmental rating Report covering pp_ the operation of thew during the previous ca endar year shall be submitted prior to May 1 of each year. Tm report shall include summaries, inte greta-tions, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistant with the objectives out1 ned in (1) the 00CM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

' 4EMfANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT pu **

b 6.9.1 R S: f r' r r d Radioactive Effluent ReleaselRep A. on of theM during the g eithf- 50 ty: efte- 3rr I rd ;M.,

previous 1 of each year. S :rth:shall efbe:;;M.= ort covering th submitted clude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the.wrt. The material provided shall be (1) con-sistent with the objectives outlinedtin the 00CM and PCP and (2) in conformance c

with10CFR50.36aandSectionIV.B.1\ofApundixIto10CFRPart50.

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MONTHLY OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or RCS safety valves, shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, D

, no laterWashingtoncopytotheR than the 15th of each month following the caiandar month covered by the report.

OPERATING LIMITS REPORT

6. 9.1. 9 Operating limits shall be established and documented in the OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle.

The analytical methods usedsto determine the operating limits shall be those previous 1 reviewed and approved by the NRC in Topical R 9272-P-A{WestinghouseReloadSafetyEvaluationsMethodel rts: 1) WCAP dated Jul

2) WCAP-8385 " Power Distribution Control and Load Followi Procedures"ydated 1985, September 1974, 3) NFSR-0016 " Benchmark of PWR Nuclear Des gn Methods" dated July 1983, and/or 4) NFSR-0081 " Benchmark of PWR Nuclear Design Methods Using the PHOENIX-P and ANC Computer Codes" dated July 1990. The operating limits shall be determined limits, core solimits, themal-hydraulic that ECCS all applicable limits nuc limits fuel thermal-mechanical (e.g. lear limits such as shutdownmargin,andtransientandaccidentanalysIslimits)ofthesafety analysis are met. The OPERATING LIMITS REPORT including any mid-c revisions or supplements thereto, shall be prov,ided upon issuance, ycle for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

"A single submittal may be made for a multi-unit station.

    • A single submittal may be made for a multi-unit station. The submittal should combine those sections that are common to all units at the station however,

' forunitswithseparateradwestesystems,thesubmittalshallspecIfythe releases of radioactive material from each unit.

BYRON - UNITS 1 & 2 6-22 AMENDMENT N0. !jb ]

\

l ADMINISTRATIVE CONTROLS j

RECORD RETENTION (Continued)

c. Records of radiation exposure for all individuals entering radiation i control areas; i

. d. Records of gaseous and liquid radioactive material released to the j environs;

e. hem

. Records of transient or operational cycles for those ente dosponents identified in Table 5.7-1; i f. Records of reactor tests and experiments; g.

Records of training and qualification for current members of the kcd4y 1m h staff; .

J t h.

Records of in-service inspections performed pursuant to these Technical Specifications; .

t 1.

Records of Quality Assurance activities required by the QA Program;

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59;
k.

i Records of meetings and results of reviews and audits performed by the Offsite Review and Investigative Function and the Onsite Review

and Investigative Function; 1.

e Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records; 1'

a.

Records of secondary water sampling and water quality; n.
Records of analysis required by the Radiological Environmental
Monitoring Program that would permit evaluation of the accuracy of 4 the analysis at a later date. This should include procedures effective at specified times and QA records showing that these

{, procedures were followed, and

{ o.

Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent i

with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

4

] BYRON - UNITS 1 & 2 6-24 AMENDMENT M. k8 j

ADMINISTRATIVE CONTROLS 4

0FFSITE DOSE CALCULATION MANUAL (00CM) (Continued) t

c. Shall be submitted to the Commission in the fom of a completa, legible copy of the entire ODCM as a part of or concurrent with the

'--i---"-' Radioactive Effluent Release Report for the period of the report in which any change to the 00CM was made effective. Each change shall be identified by markings in the margin of the affected

, pages, clearly indicating the area of the page that was changed, and

' shall indicate the date (e.g , month / year) the change was

implemented.

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BYRON - UNITS 1 & 2 6-27

  1. s eMENT NO. k $  ;

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ATTACHMENT B-2 ,

PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, OF FACILITY OPERATING LICENSES NPF-72 AND NPF-77,

- BRAIDWOOD STATION UNITS 1 & 2 Revision to: XIX XX 1-4 3/4 11-1 3/4 11-3 6-1 6-2 6-2a 6-5 6-6 6-17 ,

6-20 i 6-22 6-24 6-27

1 CHANGE

SUMMARY

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Technical Described Soecification Change Descriotion in item #

Index Change " unit' to " facility" 4  ;

1 Index Change " Semiannual" to " Annual" 1 1.18 Delete ' Semiannual" 1 3.11.1.4 Delete " Semiannual" 1 3.11.2.6.a Delete " Semiannual" 1 6.1.1 Change " unit" to " facility' 4 6.1.2 Revise description of the Shift Engineer's 3 responsibilities 6.2.1 Change " unit" to " facility' 4 6.2.2 Change " unit" to " facility" 4 Change " Operator" to " Reactor Operator' 6.2.4 Revise description of Shift Techrical Advisor; 2 ,

Delete description of specific STA work l practices Table Replace table with one that is more consistent 4 1 6.2-1 with the Standard Technical Specifications

]

(titles, notes, and format) I i

6.3 Change " unit" to " facility" 4 I Replace specific titles w;th more generic titles 6.4 Change " unit" to " facility" 4 6.8.3 Correct spelling of " Specification" 4 6.8.3.b Change " Operator" to ' Reactor Operator" 4 l

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-__.m CHANGE

SUMMARY

(continued)

Technical Described SoecificatiRD Change Descriotion in item #

6.9.1.4 Change " unit" to " facility' 4 Delete reference to initial report 6.9.1.6 Change " unit" to " facility' 4 6.9.1.7 Change the submittal frequency of the 1 radiological effluent report from semiannual to annual. Due date changed to May 1.

6.9.10.2 Change " unit" to " facility" 4 6.14.1.c Delete " Semiannual" 1 1

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l ADMINISTRATIVE CONTROLS l

PAGE l SECTION 6.1 RESPONSIBILITY................................................ 6-1 6.2 ORGANIZATION.................................................. 6-1

. FIGURE 6.2-1 (THIS FIGURE NOT USED)............................... 6-3 FIGURE 6.2-2 (THIS FIGURE NOT USED)............................... 6-4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION........................ 6-5 -

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6.3 WNET STAFF QUALIFICATIONS..................................... 6 6.4 TRAINING...................................................... 6-6 l

6.5 REVIEW INVESTIGATION AND AUDIT................................ 6-6 1

6.5.1 0FFSITE..................................................... 6-7 i Offsite Review and Investigative Function................... 6-7 Station Audit Function...................................... 6-8 Authority................................................... 6-9 Records..................................................... 6-10 Procedures.................................................. 6-10 Personne1................................................... 6-10 6.5.2 0NSITE...................................................... 6-12 Onsite Review and Investigative Functions................... 6-12 Responsibility.............................................. 6-12 Authority................................................... 6- 13 Records..................................................... 6-14 P roc ed u re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14 Personne1................................................... 6-14 6.6 REPORTABLE EVENT ACTI0N....................................... 6-15 BRAIDWOOD - UNITS 1 & 2 XIX AMENDMENT NO.

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o. l ADMINISTRATIVE CONTROLS l l l SECTION PAGE l

l 6.7 SAFETY LIMIT VIOLATION........................................ 6-15 6.8 PROCEDURES AND PR0 GRAMS....................................... 6-16

E. 9 REPORTING REQUIREMENTS........................................ 6-20 s l

6.9.1 ROUTINE REP 0RTS............................................. 6-20 C Startup Report.............................................. 6-20 .

Annual Reports.............................................. 6-20 )

l Annual Radiological Environmental Operating Report.......... 6-22  ;

< A Sem% nnual Radioactive Effluent Release Report..............

6-22 Monthly Operating Report.................................... 6-22 (

Operating Limits Report..................................... 6-22 /

Criticality Analysis of Byron and Braidwood )

Station Fuel Storage Racks................................ 6-23 <

6.9.2 SPECIAL REP 0RTS............................................. 6-23 6.10 RECORD RETENTION............................................. 6-23 )

)

6.11 RADIATION PROTECTION PR0 GRAM................................. 6-24 , j 6.12 HIGH RADIATION AREA.......................................... 6-25 <

6.13 PROCESS CONTROL PROGRAM (PCP)................................ '

6-26 6.14 0FFSITE OOSE CALCULATION MANUAL (0DCM)....................... 6-26 [ j 1

I BRAIDWOOD - UNITS 1 & 2 XX AMENDMENT NO.

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l. t j DEFINITIONS i

0FF5ITE DOSE CALCULATION MANUAL 4

! 1.18 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology ,

and parameters used in the calculation of offsite doses resulting from radio- '

active gaseous and liquid effluents, in the calculation of gaseous and liquid

'!l effluent monitoring alare/ trip setpoints, and in the conduct of the Environ-mental Radiological Monitoring Program. The ODCM shall also contain (1) the '

Radioactive Effluent Controls and Radiological Environmental Monitoring Programs

(

required by Sections 6.8.4.e and f, and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and 4.

2 212:=1 Radioactive Effluent Release Reports required by Specification <.

6. 9.1. 6 and 6. 9.1. 7. p J

l OPERABLE - OPERABILITY

! 1.19 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it-is capable of performing its specified function (s),.

and when all necessary attendant instrumentation, controls, electrical power, j cooling or seal water, lubrication or other auxi,11ary equipment that are.

1 required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

~

OPERATING LIMITS REPORT j

i 1.19.a The OPERATING LIMITS REPORT is the unit-specific document that provides

( operating limits for the current operating reload cycle. These cycle-specific 4

operating limits shall be determined for each reload cycle in accordance with

Specification 6.9.1.9. Plant Operation within these operating limits is j addressed in individual specifications.

OPERATIONAL MODE - MODE 1.20 An OPERATIONAL MODE (i.e. , MODE) shall correspond to any one inclusive l combination of core reactivity condition, power level, and average reactor

coolant temperature specified in Table 1.2.

i

! PHYSICS TESTS i

i 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation: (1) described I in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, j or (3) otherwise approved by the Commission.

5 PRESSURE BOUNDARY LEAKAGE 1

1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component j body, pipe wall, or vessel wall.

i (

1 3

1 BRAIDWOOD UNITS 1 & 2 1-4 AMENDMENTN0.,2!I

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i 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS ,

LIQUID HOLDUP TANKS i

i LIMITING CONDITION FOR OPERATION i

3.11.1.1 Deleted 3.11.1.2 Deleted 3.11.1.3 Deleted i I

)

' 3.11.1.4 The quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in.any outside tanks shall be limited to the following:

) a. Primary Water Storage Tank 5 2000 Curies, and

b. Outside Temporary Tank 1 10 Curies.

APPLICABILITY: At all times.

ACTION:

4

a. With the quantity of radioactive material in any of the above listed l g tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the events leading to this condition in the next '- '---" ' Radioactive Effluent Release Report, pursuant to Specification 6.9.1.7.
b. The provisions of Specification 3.0.3 are not' applicable.

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1 SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above

! tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materialf are being added to the tank.

(

i BRAIDWOOD - UNITS 1 & 2 3/4 11-1 AMENDMENTNO.[

(-

f RADIOACTIVE EFFLUENTS -

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t GAS DECAY TANKS i

LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall i be limited to less than or equal to 5x104 Curies of noble gases (considered as
j. . Xe-133 equivalent).

! APPLICABILITY: At all times. _.

ACTION:

! a.

i With the quantity of radioactive material in any gas decay tank exceeding the~above limit, immediately suspend all additions of radioactive material to the tank and, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, reduce the i tank contents'to within the limit, and describe the events leading j to this condition in the next S ier.;;.;d Radioactive Effluent '

Release Report, pursuant to Specification 6.9.1.7.

i b. The provisions of Specification 3.0.3 are not applicable. 7

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j SURVEILLANCE REQUIREMENTS a

! 4.11.2.6 The quantity of radioactive material contained in each gas decay tank j

shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> j when radioactive materials are being added to the tank.

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1 j BRA 70 WOOD - UNITS 1 & 2 3/4 11-3 r AMEN 0MENTNO./

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager, Braidwood Station, shall be responsible for overall

(_o J K operation bility during hisandabsence.

shall delegate in writing the succession to this responsi-l 6.1. 2 The Shift Engineer (or during Mc st>sence-frMe-control-room a-decignated individuel) shall be responsible for the centrcl room-comman,d functiom A-management-direct 4ve-to-th4-+#e ct,-+i g ne d- by-th e -V i c e - P re s i de n t 4 PWR-Operat-ions-shah-be-rehsgenpa

);mwg ne contot txe co m u pten onat4 ersonnel-on-an-annuapbsis.

daity opereHe >u e. ~ < faellJy,t  ;

6. 2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for operation and corporate management, respectively. The onsite and offsite organizations h shall include power plant. the positions for activities affecting the safety of the nuclear g

7 I

a.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through h intermediate levels to and including all operating organization positions. (y These relationships shall be documented and updated, as (

appropriate, in the form of organization charts, functional  ?

descriptions of departmental responsibilities and relationships, and (,

job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the (

?

Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activities; h Section 6 Interdepartmental Relationships. <

b. The Station Manager shall be responsible for overall # safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. [7
c. (

The Senior Vice President-Nuclear Operations shall have corporate responsibility for overall plant nuclear safety and shall tain any

[

measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant ([ 7 to ensure nuclear safety. )

(

d.

The individuals who train the operating staff and those who carry

(#

out health physics and quality assurance functions may report to the 7 appropriate onsite manager; however, they shall have sufficient 7 organizational pressures. freedom to ensure their independence from operating h FhauTy /

6.2.2 ttHH STAFF Fac;I. I The unt $taff shall be subject to the following:

j a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; and BRAIDWOOD - UNITS 1 & 2 6-1 AMENDMENTNO.M

ADMINISTRATIVE CONTROLS ,,.

UNIT STAFF (Continued) Renbr

b. Atleastonelicensedkperatorshallbeinthecontrolroomwhen l fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senio Operator shall be in the
control room; .  ;

eu+sy  ;

c. A Radiation Protection Technician,* qualified in radiation protection

. procedures, shall be on site when fuel is in the reactor; pealcr

d. All CORE ALTERATIONS shall be observed and directly supervised by I i either a licensed Senio Operator or licensed Se h 0perator Limited i

responsibilities during

, to thisFuel Handling who has no operation; other f,a 1, q concurrent [Reccrer I

e. Administrative procedures shall be developed and implemented to limit the working hours of staff who perform safety-related J functions;e.g.,licensedSeniorq0erators, licensed erators, health physics personnel, equipment l operators, and key maintenance personnel. I focll& G qaupe Re6r The amount of overtime worked by M staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12);

i f. The Assistant Superintendent Operating shall hold a Senior Reactor Operator License.

, 6.2.3 ONSITE NUCLEAR SAFETY GROUP (0NSG)

FUNCTION

6.2.3.1 The 0NSG serves as an independent safety engineering group and shall function to examine plant operating characteristics, NRC issuances, industry l advisories, REPORTABLE EVENTS and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety. The ONSG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, opera-i tions activities or other means of improving plant safety to the Safety
Assessment Manager, and the Station Manager, Braidwood Station.

. COMPOSITION 6.2.3.2 The DNSG shall be composed of at least three dedicated, full-time engineers located on site.

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

BRAIDWOOD - UNITS 1 & 2 6-2 AMENDMENT NO.

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ADNINISTRATIVE CONTROLS 6.2.3 ONSITE NUCLEAR SAFETY GROUP (ONSG) (Continued)

RESPONSIBILITIES 6.2.3.3 The ONSG shall be responsible for maintaining surveillance of plant

! activities to provide independent verification

  • that these activities are j performed correctly and that human errors are reduced as much as practical, i RECORDS

) 6.2.3.4 Records of activities performed by the ONSG shall be prepared, main-g' j tained, and forwarded each calendar month to the Safety Assessnient Manager,

.and the Station Manager, Braidwood Station. 4 4

6.2.4 SHIFT TECHNICAL ADVISOR The St: tion Contr41-Room-Engineer-(SCRE) ::y : r';: :: the Shift Technical

Advisor (STA) during ebnera,al Operating cr accident
nditi:ns. During th;;

conditiene the SC'!E cr Oth:r :n 6ty STA shall providertechnical support to the i i Shift A pervi;;r in the areas of thermal hydraulics, reactorTengineering and  !

i plant analysis with regard to the safe operation of the im4.

b mlv iW'/

b' cp h eer*

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j *Not responsible for sign-off function.

i SRAIDWOOD - UNITS 1 & 2 6-2a

AMENDMENTNO.)6 ,

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TABLE 6.2-1

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MINIMUM SHIFT CREW COMPOSITION

/

POS ION NUMBEROFINDIVIDUALSREQUIREDTOFILLPOSITIO j BOTH UNITS IN BOTH UNITS IN ONE UNIT IN MODE 1 2, 3 OR 4

MODE 1, 2, 3, MODE 5 OR 6 .

A j OR 4 OR DEFUELED ONE UNIT IN MOD 5 OR 6 OR DEFUELED i- SE 1 1 1 SF 1 None" 1 .

! RO 2 3

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A0 3 3 3 1 STA or SCRE 1 None 1

]

i Shift Su rvisor (Shift Engi eer)/ with a Senior Operator 1 SE

license

! SF -

Shift For n with a Seni r Operator license i RO -

Individual w th an Oper or license i A0 -

Auxiliary Ope tor i STA -

Shift Technical Advi r I SCRE - Station Control o Engineer with a Senior Operator License 1

(~

The Shift Crew Composition may e ne less than the minimum requirements of .

i Table 6.2-1 for a period of t ' no to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate '

j unexpected absence of on-du shift row members provided immediate action is-

! taken to restore the Shift rew' Composition to within the minimum requirements t

i l

of Table 6.2-1. This prpvision does n61 permit any shift crew position to be j unmanned upon shift cha ge due to an oncoming shift crewman being late or absent. I During any absence o the Shift Supervisor from the control room while the Unit is in MODE 1, 2, 3 r 4, an individual with valid Senior Operatc'r license shall be designated to assume the control room command function. During any i absence of the ift Supervisor from the contr%1 room while the Unit is in-

! MODE 5 or 6, individual with a valid Operator license shall be designated to  ;

i assume the c trol room command function. l i #At leas one of the required individuals must be gssigned to the designated i posit n for each unit. \ l 4

    1. At I ast one licensed Senior Operator or licensed S'enior Operator Limited to l Fu Handling must be present during Core Alterationk on either unit, who has i other concurrent responsibilities.

1 U el

] ap lace w th hsert h

{ BRAIDWOOD - UNITS 1 & 2 6-5 AMENDMENT N0. 29 i

l INSERT "A" TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION (a)(f) l POSITION (b) MINIMUM CREW NUMBER ONE UNIT IN MODE 1, 2, 3, OP. 4, AND ONE UNIT IN EACH UNIT IN MODE MODE 5, 6, OR EACH UNIT IN MODE 1, 2, 3, OR 4 DEFUELED 5, 6, OR DEFUELED SE 1 1 1 SRO 1 1 None(e)

RO(d) 3 3 2 AO(d) 3 3 3 STA(C) 1 1 None (a) The shift crew composition may be one less than the minimum requirements of Table 6.2-1 for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to accommodate unexpected absence of on-duty shift crew members, provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crew member being late or absent.

(b) Table Notation:

SE - Shift Engineer with a Senior Reactor Operator license SRO -

Individual with a Senior Reactor Operator license RO - Individual with a Reactor Operator license or a Senior Reactor Operator license AO - Auxiliary Operator STA - Shift Technical Advisor (c) The STA position may be filled by any individual who meets the commission Policy Statement on Engineering Expertise on Shift.

l (d) At least one of the required individuals must be assigned to the l designated position for each unit. l (e) At least one licensed Senior Reactor Operator or licensed Senior Reactor Operator Limited to Fuel i!andling who has no other concurrent responsibilities must be present during CORE ALTERATIONS on either unit.

(f) with either Unit in MODE 1, 2, 3, or 4, an individual with a Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. With bott units in MODE 5, 6, or  !

defueled, an individual with a SRO license or Reactor Operator license shall be designated to assume the control room command function.

Braidwood - UNITS 1&2 6-5 AMENDMENT NO.

i ADMINISTRATIVE CONTROLS l I

5 6.2.4 TECHNICAL ADVISOR (Continued)

To assure capab ity for performance of all STA functions:

l (1) The shift fore (SRO) shall participate in the SCR ift relief  !

j turnover.

(2) During the shift, the s ft engineer and t shift foreman (SRO) shall be made aware of any signifi t changes plant status in a timely manner by the SCRE.

(3) During the shift, the shift in r and the shift foreman (SRO) shall 4 remain abreast of the cur nt plant stus. The shift foreman (SRO) shall l

return to the control on two or thre times per shift, where practicable, tus. Where not practicable to to confer with the RE regarding plant i return to the trol room, the shift forem (SRO) shall periodically i check with SCRE for a plant status update. The shift foreman (SRO) .

shall n abandon duties original to reactor ope tion, unless specifically l

]

j orde by the shift engineer. l 31 STAFF QUAL 1FICATIONS l 6.3.1 Each member of the staff shall meet or exceed the minimum qualifi-2 cations of ANSI N18.1-1971, except fo e Health Physics ig;rvi: r Or Lead Depar/mmf l j ";:lth Phy:icist, who shall meet or exceed the qualifications of Regulatory i Guide 1.8, September 1975, for a Radiation Protection Manager. p j

6.4 TRAINING .

fcdf.ly

} 6.4.1 A retraining and replacement training program for the m44 staff shall i

be maintained under the direction of the Production Training Department and shall meet or exceed the requirements and recommendations of Section 5 of ANSI /

I' ANS 3.1-1978, and shall include familiarization with relevant industry j i operational experience from the program managed by Quality Programs and Assessment.

l j 6.5 REVIEW INVESTIGATION AND AUDIT 1

The Review and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have j

the responsibilities and authorities outlined below.

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1 8RAIDWOOD - UNITS 1 & 2 6-6 AMENDMENT NO. g

- .-_ - . - . - - -. . - _ . _ _ . _ _ = .-

i 6.

9 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) i

f. Written records of reviews performed in accordance with this specification %

shall be prepared and maintained in accordance with Specification 6.10. h P

) g. Editorial and Typographical changes shall be made in accordance with station procedures.

g 6.8.3 TemporarychangestoproceduresofSpecifica9tpn6.8.1above,saybe made provided: >

a. The intent of the original procedure is not altered; j b. The change is approved by two members of the plant management staff, j at least one of whom holds a Seniorr 0perator license on the Unit affected; and __ g a g e j c. The change is documented, reviewed and approved in accordance with
Specification 6.8.2 within 14 days of implementation. >4 l 6.8.4 The following programs shall be established, implemented, and maintained

i j a. Reactor Coolant Sources outside Containment 4 A program to reduce leakage from those portions of systems outside j containment that could contain highly radioactive fluids during;a 1

(

serious transient or accident to as low as practical levels. The i systems include the recirculation portion of the Containment Spray

System, Safety Injection System, Chemical and Volume Control System, j and RHR System. The program shall include the following

i

1) Preventive maintenance and periodic visual inspection requirements, and
2) Integreated leak test requirements for each system at refueling l cycle intervals or less,
b. In-Plant Radiation Monitoring j A program which will ensure the capability to accurately determine
the airborne iodine concentration in vital areas under accident j conditions. This program shall include the following

i 1) Training of personnel, I

l 2) Procedures for monitoring, and j 3) Provisions for maintenance of sampling and analysis equipment.

{ c. Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

1) Identification of a sampling schedule for the critical variables j( and control points for these variables, i

BRAIDWOOD - UNITS 1 & 2 6-17 AMENDMENT NO.

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! 4 i

ADMINISTRATIVE' CONTROLS

! l PROCEDURES AND PROGRAMS (Continued) I u

2) A Land Use Census to ensure that changes in the use of areas at i

and beyond the SITE BOUNDARY are identified and that modifica-tions to the monitoring program are made if required by the results of this census, and l l

3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the i measurements of radioactive materials in environmental sample

! . matrices are performed as part of the quality assurance program

! for environmental monitoring.

)

l 6.9 REPORTING REQUIREMENTS l

j ROUTINE REPORTS i

1 6.9.1 In addition to the applicable reporting requirements of Title 10, Code

, of Federal Regulations, the following reports shall be submitted to the Regional l Administrator of the NRC Regional Office unless otherwise noted.

J STARTUP REPORT i

, 6.9.1.1 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 i supplier, and (4) modifications that may have significantly altered the nuclear,

thermal, or hydraulic performance of the plant.

, 6.9.1.2 The Startup Report shall address each of the tests identified in the j Final Safety Analysis Report FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test l program and a comparison of these values with design predictions and specifica-

tions. Any corrective actions that were required to obtain satisfactory opera-1 tion shall also be described. Any additional specific details required in j license conditions based on other commitments shall be included in this report.

]

! 6.9.1.3 Startup Reports shall be submitted within: (1) 90 days following com-i pletion of the Startup Test Program, (2) 90 days following resumption or com-mencement of commercial power operation, or (3) 9 months following initial j criticality, whichever is earliest. If the Startup Report does not cover all

! three events (i.e., initial criticality, completion of Startup Test Program, and i

resumption or commencement of commercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

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ANNUAL REPORTS fae;l:{y

6.9.1.4 Annual Reports covering the activities of the w44 as described below l for the previous calendar year shall be submitted prior to march 1 of each
year. '" 4 '+' ' -----*-"'"-""i"-d - - * - - + " " ' - ' ' " -

fe!!cr n; 4a1tfe! criticelity.

4 i 8RAIOw000 - units 1 a 2 6-20 anEu0nexT n0. g 9

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a ADMINISTRATIVE CONTROLS l REPORTING REQUIREMENTS (Continued)

I-1SaiIdy(ANNUALRADIOLOGICALENVIRONMENTALOPERATINGREPORT*

j 6.9.1.6 The Annual Ra.diological Environmental Operating Report covering the operation of the 844 during the previous calendar year shall be submitted i

prior to May 1 of each year. The report shall include summaries, interpreta-

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tions, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material'provided shall be

consistent with the objectives outlined in (1) the ODCM and (2) Sections l IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

h SEMIANNUAL RADI0 ACTIVE CFFLUENT RELEASE REPORT ** yed I'mr h 6.9.17 3 kni::m!- Radioactive Effluent ReleaseJaport covering the opera-

!' b'Il tion of the % 44 during the previous S :: th Of rper: tier shall be submitted v l . wi4.h" 50 dry :fter R = y 1 : d Aly 1 of each year. The report shall in-

!M q l clude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the . The material provided shall be (1) con-sistent with the objectives outline in the ODCM and PCP and (2) in conformance j with 10 CFR 50.36a and Section IV.B.1 of Appendix I,to 10 CFR Part 50.

MONTHLY OPERATING REPORT focl@7

! 6.9.1.8 Routine reports of operating statistics and shutdown experience, j including documentation of all challenges to the PORVs or RCS safety valves, i shall be submitted on a monthly basis to the Director, Office of Resource

! Management, U.S. Nuclear Regulatory Commission,-Washington, D.C.- 20555, with a j copy to the Regional Administrator of the NRC Regional Office, no later than

the 15th of each month following the calendar month covered by the report.

j OPERATING LIMITS REPORT

6. 9.1. 9 Operating limits shall be established and documented in the OPERATING i LIMITS REPORT before each reload cycle or any remaining part of a reload cycle, i The analytical methods used to determine the operating limits shall be those previously reviewed and approved by the NRC in Topical Reports: 1) WCAP l 9272-P-A " Westinghouse Reload Safety Evaluations Methodology" dated July'1985, j 2) WCAP-8385 " Power Distribution Control and Load Following Procedures" dated l September 1974, 3) NFSR-0016 " Benchmark of PWR Nuclear Design Methods" dated i j July 1983, and/or 4) NFSR-0081 " Benchmark of PWR Nuclear Design Methods Using

. the PHOENIX-P and ANC Computer Codes" dated July 1990. The operating limits i shall be determined so that all applicable limits (e.g., fuel thermal-mechanical l limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as j' shutdown margin, and transient and accident analysis limits) of the safety

analysis are met. The OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each '

i reload cycle, to the NRC Document Control Desk with copies to the Regional l Administrator and Resident Inspector.

i I- "A single submittal may be made for a multi-unit station.

    • A single submittal may be made for a multi-unit station. The submittal should I

combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the g

releases of radioactive material from each unit.

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BRAIDWOOD - UNITS 1 & 2 6-22 AMENDMENTNO.[ Q 4

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

l ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued)

c. Records of radiation exposure for all individuals entering radiation i control areas;
d. Records of gaseous and liquid radioactive material released to the l environs; '

fc. didy ,

e. Records of transient or operational cycles for those unit components I identified in Table 5.7-1;
f. Records of reactor tests and experiments;
g. Records of training and qualification for current members of the e &t staff; Soo lo +1
h. Records of in-service inspections performed pursuant to these Technical Specifications;
i. Records of Quality Assurance activities required by the QA Program;  ;
j. Records of reviews perfor**d for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59;
k. Records of meetings and results of reviews and audits performed by
the Offsite Review and Investigative Function and the Onsite Review and Investigative Function;
1. Records of the service lives of all hydraulic and mechanical snubbers required by Specification 3.7.8 including the date at which the service life commences and associated installation and maintenance records;
m. Records of secondary water sampling and water quality;
n. Records of analysis required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed, and
o. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

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BRAIDWOOD - UNITS 1 & 2 6-24 AMENDMENT NO.

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1 ADMINISTRATIVE CONTROLS 0FFSITE DOSE CALCULATION MANUAL (ODCM) (Continued) 1

c. Shall be submitted to the Commission in the form of a complete,  !

legible copy of the entire ODCM as a part of or concurrent with the {

k ;i;rr.=' Radioactive Effluent Release Report for the period of the i report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected ,

pages, clearly indicating the area of the page that was changed, and i shall indicate the date (e.g., month / year) the change was  !

implemented.

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BRAIDWOOD - UNITS 1 & 2 6-27 AMENDMENT NO.,3s b 7

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ATTACHMENT C l EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATIONS Commonwealth Ediso'n has evaluated this proposed amendment and determined that it involves no significant hazards considerations. According to 10CFR50.92(c), a ,

proposed amendment to an operating license involves no significant hazards if operation of the facility in accordance with the proposed amendment would not:

- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or
3. Involve a significant reduction in a margin of safety.

The proposed amendment makes several changes to the Administrative Controls in Section 6 of Technical Specifications for Byron and Braldwood stations. The proposed changes include (1) a change to the submittal frequency of the Radiological Effluent Release Report, (2) a revision to the Shift Technical Advisor description, (3)  !

clarification of the Shift Engineer's responsibilities, and (4) editorial changes. The j references to the Semiannua! Radiological Effluent Release Report are also revised in other sections of Technical Specifications.

A. The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed changes to Section 6 of Technical Specifications do not affect any accident initiators or precursors and do not change or alter the design ,

assumptions for the systems or components used to mitigate the consequences of an accident.

The proposed changes are administrative in nature and provide clarification. l These changes provide consistency with station procedures, programs, the Code l of Federal Regulations, other Technical Specifications, and Standard Technical Specifications. These changes do not impact any accident previously evaluated in the UFSAR.  !

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, Attachment C Page 2 1

B. The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. l I

The proposed changes do not affect the design or operation of any system, i structure, or component in the plant. There are no changes to parameters governing plant operation; no new or different type of equipment will be installed.

. The proposed changes are considered to be administrative changes. All i responsibilities described in Technical Specifications for management activities l will continue to be performed by qualified individuals. 1 l

C. The proposed changes do not involve a significant reduction in a margin of l safety. )

The proposed changes do not affect the margin of safety for any Technical Specification. The initial conditions and methodologies used in the accident analyses remain unchanged, therefore, accident analysis results are not impacted.

The proposed changes are administrative in nature and have no impact on the margin of safety of any Technical Specification. They do not affect any plant safety parameters or setpoints. The descriptions for the Shift Technical Advisor and Shift Engineer are clarified, however, include no reduction to their responsibilities.

Based on the above evaluation, Commonwealth Edison has concluded that these )

changes do not involve significant hazards considerations. 1

l ATTACHMENT D ENVIRONMENTAL ASSESSMENT Commonwealth Edison Company has evaluated the proposed amendment against the criteria for and identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21. Comed has determined that the

. proposed change meets the criteria for a categorical exclusion as provided for under 10CFR51.22(c)(10). This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10CFR50, and it changes administrative procedures or requirements.

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