ML20246L250

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Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,deleting Tech Spec Figures 6.2-1 & 6.2-2 by Replacing Figures W/Narrative Description of Offsite & Onsite Organizations Functional Requirements
ML20246L250
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/26/1989
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246L227 List:
References
NUDOCS 8907180377
Download: ML20246L250 (35)
v • d • e


Text

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UNITED STATES p, NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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p CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAM NECK PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.118 License No. DPR-61

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

A. The application for amendment by Connecticut Yankee. Atomic Power (thelicensee), dated March 13, 1989 as supplemented April 28, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C. . There is reasonable assurance (1) 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 defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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8907180377 890626 DR ADOCK 050 3

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2. Accordingly, the license is amended by changes to the Technical Spec:fications 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.118, are hereby incorporated in tl}e license.

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

3.- This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REG LATORY COMMISSION Jh F. Stolz, ' irect oj ct Directointe 4 0 ion of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 26, 1989 4

6 4 ATTACHMENT TO LICENSE AMENDMENT NO.118 FACILITY OPERATING LICENSE NO. DPR-61 DOCKET NO. 50-213~

Replace the following pages of the Appendix.."A" Technical Specifications'with the enclosed pages. The revised pages are identified by amendment number

- and contain vertical lines indicating the areas of change.

Remove- 13 sert IV IV 6-1 6-1 6-la 6-2 6-2 6-3 6-3

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111D11 l ADMINISTRATIVE CONTROLS u

n L SECTION 6.0 ADMINISTRATIVE CONTROLS gggg

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' s.1 RESPONSIBILITY ................................................ '6-1 6.2 '0RGANIZATIDN 6.2.1 'Offsite and Onsite ......... ............................... 6 ]; '

6.2.2' ' Facility. Staff .............................................6-1 6.3 FACILITY STAFF QUALIFICATIONS ................................. 6-5 .

6.4 TRAINING ...................................................... 6-5 .

6.5 ' REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE .

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6.5.1.1 Function ................................................... 6-5 6.5.1.2 Composition ................................................ 6-5 6.5.1.3 Alternates ................................................. 6-6 6.5.1.4 Meeting Frequency .......................................... 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 Records .................................................... 6-7  ;

6.5.2 NUCLEAR REVIEW BOARD

-6.5.2.1 Function ................................................... 6-8 6.5.2.2 Composition .............................................,... 6-9 j 6.5.2.3 consultants ................................................ 69

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HADDAM NECK PLANT IV Amendment No. 118 l

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY l 6.1.1 The Station Superintendent shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of '.he nuclear power plant,

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

established and defined for the highest management levels through j intermediate levels to and including all operating organization i positions. These relationships shall be documented and updated, as j 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 Topical Report.

b. The Station Superintendent shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant. *
c. The Senior Vice President, Nuclear Engineering and Operations, shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d. The individuals who train the o7erating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF

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

l HADDAM NECK PLANT 6-1 Amendment No. 118 i

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6.0.JMINISTRATIVE CONTROLS L

FACILITY STAFF (Continued)

b. At leastione. licensed Operator shall be' in the control room when -

fuel is in the reactor.

  • c.' At least two licensed Operators shall- be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips. -
d. An individual qualified in radiation protection procedures shall be on site when fuel is'in the reactor,
e. ALL CORE. ALTERATIONS shall be directly supervised by either a licansed Senior Reactor operator or Senior Reactor Operator limited to fue) handling who has no other concurrent responsibilities during this operation.

Anfire brigade of five-(5) members shall be maintained on site at f.

all times. This excludes two (2) members of the. minimum shift-  !

complement- necessary for safe shutdown of the plant and any personnel required for other essential functions during a fire '

emergency.

The: brigade crew composition may be one less than the minimum requirement for a period of time 'not to exceed 2-hours in order to accommodate unexpected absences, g? Administrative procedures shall. be developed and implemented - to limit the working hours of unit staff who perform safety-related functions. These procedures should follow the general guidance of the NRC ' Policy Statement on working hours (Generic - Letter. No.

82-12). '-

l HADDAM NECK PLANT 6-la Amendment No. 118

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a HADDAM NECK PLANT 6-2 Amendment No. 118

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4 HADDAM NECK PLANT 6-3 Amendment No. 118

. UNITED STATES

'H ' NUCLEAR REGULATORY COMMISSION ' J b M7 8-

,' ', gc 3 y WASHINGTON, D. C. 20665 :

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n NORTHEAST NUCLEAR ENERGY COMPANY-DOCKET NO. 50-245 L MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE

. Amendment No. 33 l License No. DPR-21

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

A. The' application for amendment by Northeast Nuclear Energy Company (thelicensee),datedMarch 13, 1989 as supplemented April 28, 1989 complies with the standards and requirements of the Atomic Energy Act.

of 1954, as amended (the Act), and the Consission's rules and regulations set forth in 10 CFR Chapter I; 8.- The facility will operate in confomity with the application, the-provisions of the' Act, and the rules and regulations of' the Commission; C." There is reasonable assurance (1) 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 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-21 is hereby

- amended to read as follows: ,

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised '

through Amendment No. 33, 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 the date of issuance, to be implemented within 30 days of issuance..

FOR THE NUCLEAR REGU TORY COMMISSION J hn 1F. Stolz, Direct r r et Directorate sion of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 26, 1989 l

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ATTACHMENT-TO LICENSE AMENDMENT NO. 33 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245-

l. Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by' amendment number

. and contain. vertical lines indicating the areas of change.

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.L Remove Insert

'6-1 1 6-la 6-2. 6-2 3 6-3 4

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-m-_ ._______________________.________._____m_ _ . .- __m. _ _ . . _______.__m__u__2_. _ _ _ . _ _ _ _ _ . . - _ _ _ . ._ ._ _ _ _ _ _ _ _ _ _ _ . _ . _ . _ . . _ _ . _ _ - _ _ . _ _ _ _ _ _ ___1 __ .- . _ _ _ _ _ _ _

, l4; IADMINASTRATIVE (,0NTROLS '

. 6.1 RESPONSIBILITY ,

-6.1.1 The Station Superintendent shall be responsible for overall- operation of the Millstone Station Site while the Unit Superintendent shall be responsible for; operation of the unit. The Station Superintendent and Unit .

e Superintendent shall each delegate, in writing, the succession to these responsibilities during their absence.

5.2 ORGANIZATION .

6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear .

power plant.

a. Lines of authority,- responsibility, and com unication shall be-established and defined for the higher management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip-tions of departmental responsibilities and relationships,'and job-descriptions for key personnel positions, or in equiralent forms of documentation. These requirements shall be documented in the Quality Assurance Topical Report.
b. The' Station Superintendent shall be responsible for overall unit safe operation and shall have control over tho~se onsite activities necessary for safe operation and maintenance of the plant.

c .* The= Senior Vice President, Nuclear Engineering and cgrations-shalt have ~ corporate responsibility for overall-plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staN in. operation, maintaining, and providing technical support to the plant 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 appropriate onsite manager; however, they shall have roufficient organizational freedeom to ensure their independence from operating pressures.

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6.2.2 FACILITY STAFF

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b. At least one licensed Operator shall be in the control room when fuel is in the reactor,
c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

Millstone Unit 1 6-1 Amendment No. 33

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. ADMINISTRATIVE CONTROLS

' FACILITY STAFF (Continued) ,

d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.(Table 6.2-1)
e. ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Opera-tor or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f. A' site Fire Brigade of at least 5 member's shall be maintained onsite at all times.(Table 6.2-1) The Fire. Brigade shall not
  • include 2 members of the minimum shift crew necessary for safe-shutdown of the unit or any personnel required for other essential functions during a fire emergency.
g. ' Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions. These procedures should follow the general guidance of the NRC Policy Statement on working hours (Generic Letter No. 82-12).

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a Millstone Unit 1 6-la Amendment No. 33

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l Millstone Unit 1 6-2 Amendment No. 33 l

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Millstone Unit 1 6-3 Amendment No. 33 e

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-l[ g- NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20655 k * . . .

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j NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 License No. DPR-65

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

A. The application for amendment by Northeast Nuclear Energy Company (the licensee), dated March 13, 1989 as supplemented April 28, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the appliestion, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and J

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. ,

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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-65 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as. revised through Amendment No.142, are hereby incorporated in the licer.se.

The licensee shall ooerate the facility _in accordance with the Technical Specifications.

3.- This. license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.

FOR THE NUCLEAR REGU ATORY COMMISSION

$3hA 'C -

Joh F. Stolz, Directo Pr ject Directorate I vision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 26, 1989 4

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ATTACHMENT TO LICENSE AMENDMENT NO.142-FACILITY OPERATING LICENSE NO. OPR-65 DOCKET NO. 50-336 Replace the following pages of the Apper fix A Technical Specifications with the enclosed pages. . The revised pages are identified by amendment number and cont,ain vertical lines indicating the areas of change. The corresponding overle"/ pages are provided to maintain document completeness. .

Remove Insert XVI XVI 6-1 6-1 6-la 6-la 6-lb j 6-2 6-2 6-3 6-3 i

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. y l, ADMINISTRATIVE CONTR0LS' .

IECIIDM f.Afd 6.1' RESPONSIBILITY ............................................... 6-1 1.2_ ORGANIZATION ................................................ 6-1 Offsite and 0nsite.......................................... d-1 Facility Staff ............................................ 6-1 .

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l 6.3 FACILITY STAFF QUALIFICATIONS .................................. 6~Ia l

6.4 TRAINING ..................................................... 6-5 6.5 REVIEW AND AUDII 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

Function ......................................:........... 6-5 Composition ............................................... 6-5 Al t e rn a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 I

Meeting Frequency ......................................... 65

= Quorum ..................................................'.. 66 Responsibilities .......................................... 6-6 Authority ................ ................................ 6-7 Records ...............................................-.... 6-7 6.5.2 SITE OPERATIONS REVIEW COMMITTEE (50RC)

Function ..............................,.................... 7 Composition ............................................... 6-7 Alternates ................................................ 6-8 ,

Meeting Frequency ......................................... 6-8 Quorum .................s,.................................. 6-8 Responsibilities .......................................... 6-8 Authority ................................................. 6-9 Records ................................................... 6-9 1

MILLSTONE - UNIT 2 XVI Amendment No. 104, 142 1

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4 INDEX ..

4 DESIGN FEATURES 94 SECTION PAGE

5.1 ' SITE Exclusion Area................................................ 5-1 Low Popul a ti on Zohe . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 Fl ood Con tro1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5- 1 5.2 CONTAINMENT Configuration................................................. 5-1 Design Pressure and Temperature............................... 5-4 Penetrations................................................... 5-4 -

5.3 REACTOR CORE Fuel Assemblies.............................................'.. 5-4 Control Element Assemblies.................................... 5-4 5.4 REACTOR COOLANT SYSTEM -

Design Pressure and Temperature.............................. 5-4 Vo 1 tane . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 - 5 5.5 EMERGENCY CORE COOLING SYSTEMS.............. ...... ........... 5-5 5.6 FUEL STORAGE C r i ti ca l i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5- 5 Drainage....................................................... 5-5 Capacity...................................................... 5-5 l

5.7 SEISMIC CLASSIFICATION........................................ 5-5 5.8 METEOROLOGICAL TOWER LOCATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-6 5.9 SHORELINE PROTECTION.......................................... 5-6 l

l MILLSTONE - UNIT 2 XV Amendment No. JM ,109

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/ ADMINISTRATIVE' CONT @LS

. 6.I RESPONSIBILITY-6.1.1' The Station' Superintendent shall be responsible for overall opera-tion of the Millstone Station Site while Lie Unit Superintendent shall' be responsible for operation of the unit. The Station Superintendent and Unit Superintendent shall each delegate in writing the succession to these respon-sibilities during their absence.

l 6l2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS i

Onsite and offsite organizations shall be established for unit' operation 'and corporate managament, respectively. The onsite and offsite organizations-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 higher management levels through , i intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descrip-tions of departmental responsibilities and relationships, and job deteriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Quality Assurance Topical Report.
b. The Station Superintendent shall be' responsible for overall unit safe operation and shall have control over those.onsite _ activities necessary for safe operation and maintenance of the plant.

E. The Senior Vice President, Nuclear Engineering.and Operations shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operation, maintaining, and providing technical support to the plant to . ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may repor.t to the appropriate onsite manager; however, they shall have sufficient organization freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFF

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown H Table 6.2-1.
b. At least one licensed Operator shall be in the control room when fuel is in the reactor,
c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

Millstone - Unit 2 6-1 Amendment No. 45. ff, 18, 92, 106, I26, 142

. 4 kDMINISTRATIVEC0HTROLS (

FACILITY STAFF fC0flTINUED)

d. An individual qualified in radiation protection procedures  :

shall be on site when fuel is in the reactor. (TableG.2-1)

e. ALL CORE ALTERATIONS after the initial fuel leading shall be directly supervised by either a licensed Senior Reactor Opera-tor or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
f. A site Fire Brigade of at least 5 members shall be mair.tained onsite at all times. (Table 6.2-1) The Fire Brigade shall not ,

include 2 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

g. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-relat-ed functions. These proced' Ares should follow the general guidance of the NRC Policy Statement on working hours (Generic  :

. Letter No. 82-12). ,

1 E.3 FACILITY STAFF 00ALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for:

a. The Radiation Protection Manager who shall meet or exceedi the qualifications of Regulatory Guide 1.8, Revision 1,.

b) The Shift Technical Advisor (STA) who shall meet the requirements of Specific, ion 6.3.1.b.1 or 6.3.1.b.2.

1. Dual-role individual: Must hold a senior reactor operator's license at Millstone Unit No. 2, mee.t the STA training criteria of NUREG-0737, Item I . A.1.1, and meet one of the following educational alternatives:
a. Bachelor's degree in eng.ineering from an accredited institution; .
b. Professional Engineer's license obtained by the successful completion of the PE examination;
c. Bachelor's degree in engineering technology from an accredited institution, including course work in the physical, mathematical, or engineering sciences;
d. . Bachelor's degree in a physical science from an accredited institution, including course work in the physical, '

mathematical, or engineering sci.ences; Millstone - Unit 2 6-la Amendment No. 136, 142 b__ =_ _ _ _ _ --

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' ADMINISTRATIVE CONTROLS.

e. S:ccessful completion of the Memphis State University?

-(MSU) STA program. (Note: This alternative is only acceptable for individuals who have completed the program prior to December 31, 1986); or

f. Successful completion of the Thames Valley state Technical College associate's degree in Nucleer Engineering Technol-ogy program, provided that the. individual was enrolled in the program by October 1,-1987.
2. Dedicated STA: Must meet the STA training criteria of NUREG-0737, Item I.A.I.1, and have received specific training in plant design, and response and analysis of the plant for

T. .

o Millstone - Unit 2 6-lb Amendment No. 142 l

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'l Millstone - Unit 2 6-2 Aaendment No. 142

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1 Millstone - Unit 2 6-3 Amendment No. 142 I

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.#f ***{Gg' UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION

$ j WASHINGTON, D. C. 206B5

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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.

DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. NPF-49

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

A. The application for amendment by Northeast Nuclear Energy Company (thelicensee),datedMarch 13, 1989 as supplemented April 28, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commir,sion's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) 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 defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance w'.th 10 CFR Part 51 of the Connission'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. NPF-49 is hereby amended to read as follows:

(2) Technical Specifications l

The Technical Specifications contained in Appendix A, as revised '

through Amenmeent No. 36 , and the Environmental Protection Plan -

contained in Appenoix B, both of which are attached hereto are hereby, incorporated in the license. The licensee shall operate the facility in accordarce with the Technical Specifications and the Environmental Prcte tion Plan.

3. This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.

F THE NUCLEA GUL ORY COMMISSION

/

hn . Stolz, Director-ro ect Directorate I-ision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 26, 1989

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ATTACHMENT TO LICENSE AMENDMENT NO.36 FACILTIY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines ' indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness. ,

Renove Insert xviii xviii 6-1 6-1 6-2 6-2 6-3 6-3 6-4 . 6-4 6-7 6-7 e

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- i 4 INDEX 4 , .-

DESIGN FEATURES SECTION

'PAGE 5.1 SITE 5.1.1 : EXCLUSION AREA................................................ . 5-1 5.1. 2 LOW POPULATION Z0NE........................................... 5-1

-5.1.3- SITE BOUNDARY FOR LIQUID AND GASEOUS EFFLUENTS................. 5-1 ,

FIGURE 5.1-1 EXCLUSION AREA......................................... 5-2.

' FIGURE 5.1-2 LOW POPU LATION 20NE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-3 FIGURE 5.1-3 SITE BOUNDARY FOR LIQUID AND GASEOUS EFFLUENTS......... 5-4 5.2 CONTAINMENT

5. 2.1 CONFIGURATION................................................. 5-1

~ 5.2.2' DESIG'N PRESSURE AND TEMPERATURE....... ..................... 5-1 5.3 REACTOR CORE- -

5.3.1 FUEL ASSEMBLIES............................................... 5-5 5.3.2 CONTROL ROD ASSEMBLIES........................................ 5-5 5.4 REACTOR COOLANT SYSTEM

5. 4.1 DESIGN PRESSURE AND TEMPERATURE............................... 5-5 5.4.2 V0LUME........................................................ 5-5
5. 5 METEOROLOGICAL TOWER LOCATION................................... 5-5 5.6 FUEL STORAGE 5.6.1 CRITICALITY................................................... 5-6 5.6.2 DRAINAGE...................................................... 5-6
5. 6. 3 CAPACITY...................................................... 5-6
  • 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT............................. 5-6 TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS.................... 5-7 MILLSTONE - UNIT 3 xvii .

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l ADMINISTRATIVE CONTROLE SECTION P.ME 6.1 RESPONSIBILITY ................................................ 6-1 6.2 -ORGANIZATION .................................................. 6-1 6.2.1 0FFSITE AND ONSITE .......................................... 6-1 6.2.2 FACILITY STAFF ...,.......................................... 6-1 FIGURE 6.2-1 .0FFSITE ORGANIZATION .......... DELETED................ 6-3 -

FIGURE 6.2-2 UNIT ORGANIZATION ............. DELETED........../.. .. 6-4 TABLE'6.2-1 MINIMUM SHIFT CREW COMPOSITION ......................... 6-5 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

Function'.................................................... 6-6 Composition ................................................. 6-6 Responsibilities ..............................:............. 6-6 Records .........................'............................ 6-6 1

6. 2. 4 = SHI FT TECHNICAL ADVISOR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6.3 FACILITY STAFF 00ALIFICATIONS ................................. 6-7 I

6.4 TRAINING ...................................................... 6-7 3 6.5 REVIEW AND AUDIT ............................................... 6-7 1 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)

Function .................................................... 6-7 l Composition .................................................' 6-7 Alternates .................................................. 6-8 l 1

Meeting Frequency ... ....................................... 6-8

{

l Quorum ...................................................,.. 6-8 l Responsibilities ............................................ 6-9 )

l Authority ..................................;................ 6-9 Records ..................................................... 6-9 MILLSTONE - UNIT 3 xviii ' Amendment Mc. 35  !

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' ADMINISTRATIVE CONTROLS

'6.1 RESPONSIBILITY 6.1.1 - The Station Superintendent shall be responsible for overall operation of the . Millstone Station site while the Unit Superintendent shall be responsible for operation of the unit. The Station Superintendent and Unit Superintendent .shall. each delegate in writing the sucession to these responsibilities during their absence..

6.2 ORGANIZATION

6.2.1 0FFSITE AND ONSITE ORGANIZATIONS ,

Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations 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-positions. 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 Topical Report.
b. The Station Superintendent shal'1 be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
c. The Senior Vice President, Nuclear Engineering and Operations, shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant 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 appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 FACILITY STAFE .

a. Each on-duty shift shall be conposed of at least the minimum shift crew composition shown in hble 6.2-1; MILLSTONE - UNIT 3 6-1 Amendment NO. 36 J l

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. J ADMINISTRATIVE CONTROLS .

FACILITY STAFF (Continued) 1

b. At least one licensed Operator shall be in the control room when i fuel is in the reactor. In addition, whil
  • the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the ',

control room;

c. At least two licensed Operators shall be present in the control room

- during reactor startup, scheduled reactor shutdown and during .

recovery from reactor trips. l I

I

. d. A Health Physics Technician

  • shall be on site when fuel is in the reactor;
e. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Sanier Reactor Operator or licensed Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;
f. A site Fire Brigade of at least five members
  • shall be maintained on site at all times. The Fire Brigade shall not include two members of the minimum shift crew necessary for safe shutdown of the unit and any personnel. required for other essential functions during a fire emergency; and
g. Administrative procedures shal1 be developed and implemented to limit the working hours of unit staff who perform safety-related functions. These procedures should follow the general guidance of

= the NRC Policy Stateuent on working hours (Generic Letter No. j 82-12). .

1

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

the required positions. ,

MILLSTONE - UNIT 3 6-2 Amendmant No. 36

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MILLSTONE - UNIT 3 6-4 Amendment No. 36 l

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ADMINISTRATIVE CONTROLS' 6.3 FACILITY STAFF QUALIFICATIONS s

6.3.1 Each member 'of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, Revision 1, May 1977. The licensed Operators and Senior .

Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.

6.4 TRAINING -

6.4.1 A retraining and replacement training program for the facility staff {

shall be maintained under the direction of the Station Superintendent. and shall meet or exceed the requirements and recommendations of Section 5.5 of .

ANSI N18.1-1971 and Appendix A of 10 CFR. Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Training Supervisor and shall meet or exceed the reqdrements of Section 27 of the NFPA Code-1975, except for Fire Brigade training sessions which shall be held at least quarterly.

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

FUNCTION .

6.5.1.1 The PORC shall function to advise the Unit Superintendent on all matters related to nuclear safety.

COMPOSITI'ON 6.5.1.2 The PORC shall be composed of the:

Chairman: Unit Superintendent Vice Chairman and Member: Operations Supervisor l Member: Maintenance Supervisor '

Member: Instrument and Control Supervisor  !

Member: Reactor Engineer Member: Engineering Supervisor or Startup Supervisor

  • Member: Station Services Superintendent or Quality Services Supervisor or Radiological Services Supervisor i Member: Staff Engineer **

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  • When position is staffed.

4

    • The Staff Engineer member of the PORC shall have an academic degree in '

engineering er physical science field; and, in addition, shall have a five years technical experience, of which a minimum of three years shall i be in the nuclear power plant industry. d MILLSTONE - UNIT 3 67 Amendment No. 16 1 ,

j ADMINISTRATIVE CONTROLS .

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ALTERNATES 6.5.1.3 All alternate members shall ~ be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at a:V one time.

NEETING FREDUENCY 6.5.1.4 The PORC shall meet at least once per calendar month and es convened by the PORC Chairman.

ElDEE

. I 6.5.1.5 The quorum of the p0RC shall consist of the Chairman or Vice Chairman l or Station Superintendent and four members including alternatas.

RESPONSIBILITIES

  • 6.5.1.6 The PORC shall be responsible for:
a. Review of: -(1) all procedures, except common site procedures, required by Specification 6.8 and changes thereto, and (2) any other proposed procedures or chsnges thereto as determined by the Unit Superintendent to affect nuciear safety;
b. Review of all proposed tests and experiments that affect nuclear safety;
c. Review of all proposed changes to Sections 3.0-5.0 of these Technical Specifications;
d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety;
a. Investigation of all violations of. the Technical Specifications, including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence, to the Vice President-Nuclear Operations and to the Chairsan of the Nuclear Review Board; f.- Review of all REPORTABLE EVENT 5;
g. Review of facility operations to detect potential safety hazards;
h. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Chairman of the Nuclear Review Board or the Station Superintendent; and
1. Render determinations in writing with regard to whether or not each item considered under Specification 6.5.1.6a. through d. above con-stitutes an unreviewed safety question.
j. Review of Unit Turbine Overspeed Protection Maintenance and Testing Program and revisions.thereto.

MILLSTONE - UNIT 3 6-8 Amendment No. 34 MAY 2 31989 3

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