ML20244C864

Amends 95 & 92 to Licenses DPR-21 & DPR-65,respectively, Changing Tech Specs to Comply W/Final Rule on Licensed Operator Staffing

ML20244C864
Person / Time
Site:	Millstone
Issue date:	02/16/1984
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20081B023	List: ML20244C864
References
GL-86-04, GL-86-4, TAC-44104, TAC-67187, TAC-67188, TAC-67189, NUDOCS 8403060459
Download: ML20244C864 (17)

Text

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. UNITED STATES

, . . [) " ' f >&g NUCLEAR REGULATORY COMMlRRION

'% s WASHING TO N, D. C. 20665 E-THE CONNL jut LIGHT AND POWER COMPANY ,

1

_ WESTERN M%5ACHUSETlS ELECTRIC COMPANY AND.

N_0RTHEAST NUCLEllFTNERGY COMPANY

< DOCKET NO. 50-245 -

MLLSTONENUCLEARPOWERSTATION,UNITNO.1 A_MENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 95 License No. DPR-21

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

A. The application for amendment by the Connecticut Light and Power Company, Western Massachusetts Electric Company and Northeast i Nuclear Energy Company (the. licensees) dated October 4,1983 J complies with the standards and requiremerits of the Atomic Energy

. Act of 195a, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; q

B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the .

L Commission; C.

There is reasonable assurance (1) that the activities authorized i by the 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 ininical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this anendment is in accordance with 10 CFR Part '

51 of the Comnission's regulatir.ns and all applicable requirements have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specificatier.s as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional Operating License f;o. DPR-21'is hereby amended to read as follows:

(2) Technical Specifications The Technical' specifications contained in Appendices A-and B as revised through Amendment No. 95 are hereby incorporated in the license. Northeast Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COM41SSTON Denn ute fiel , Chief Operating Rer.ctors ranch 45 Division of Licensing

. A'.technent:

Changes:to the Technical-

~ Specifications 4

Date of_!ssuance: February 16, 1984

- - _ _ _ _ __ _ _ _ _ --__m

ATTACHMENT TO LICENSE AMENDMENT NO. es PROVISIONAL OPERATING LICENSE NO. DPR-21 M -

LICENSE AVENDMENT NO. ._

FACILITY OPERATING LICENSE NO. 0,P_R-65 DOCKET NOS. 50-245/336 Revise the Aprendix A Technical Specifications by removing the pat 0s identified below and inserting.the enclosed pages. The revised pages the areathe include captioned amendment nunbers and marginal lines indicating of change.

Enit,,1: M 6-1 6-4 6-16 Unit ? Paces

• i 6-1 6-4 i 6-16 i .

• over M T ptpts 6-2, 6-3, and 6-15 are included for maintain ino document

. completeness.

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4 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 the Millstone Station Site while the Unit Superintendent operation of the unit.

each dele The Station Superintendent and Unit Superintendent shall absence. gate in writing the succession to these responsiollities during their 6.2 ORGANIZATION  !

OFFSITE _

6.2.1 shall be as shown on Figure 6.2-1.The Offsite organization for facility ma FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 e.rr.'

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.21.

b.

Atinleast is one licensed Operator shall be in the controi rr.,m when fuel the reactor.

w c.

At leastreactor during two Ucensed start-up, Operators shall be present in the control room I

recovery from reactor trips, scheduled reactor: shutdown and during

d. ,

An individual qualified in radiation protection procedures shall be on site when fuelis in the reactor.#

a e.

ALL CORE ALTERATIONS after the initial fuel leading shall be directly supervised by either a licensed Senior Reactor Operato or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilltles during this operation.

f.

A site at Fire Brigade of at least 3 members shall be maintained onsite all times.#

The Fire Brigade shall not include 2 members of the minimum shift crew necessary for safe shutdown of the unit or any personnel emergency. required for other essential functions during a fire 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each of qualifications member of the facility staff shall meet or exceed the minimum ANSI N18.1-1971 for comparable positions, except for (1) the Regulatory Guide 1.8, Revision 1, and (2) the Shift Tec have a Sachelor Degree or equivalent in a scientific or engineering discipline with specific transients training in plant design, and response and analysis of the plant for and accidenti, sSee Note on Page 6 6 Amendment No. 34hS,'d,66,39,6. 95 6-1

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,TABL E 6.2-1 * * *

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MINIMUM SHIFT-CREW COMPOSITION # ,

APPLICABLE MODES .

LICENSE CATEGORY 1, 2, & 3 *

• 4 & 5(/F SOL 2 1*

OL 2 1 1

Non-Licensed 2 I  !

. Shin Technical Advisor *** 1 None Required Limited to Fuel Handling individual supervision CORE ALT Initial fuel Joading.

1. The above shift crew composition and the qualified health physics ter:hnician 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 unexpected absence provided expeditious actions are taken to fill the required positions.

STARTUP/ HOT STANDBY (any** Reactor Mode Switch Fosition is in average coolant temperature), and HOT SHUTDOWN (average coolant temperature greater than 2120F), respectively.

1. 1. Reactor Mode Switch Position is in SHUTDOWN (average coolant temperature less than 212W and REFUELING (average coolant temperature less than 2120F),

respectively.

• • • The Shift Technical Advisor position may be filled by an on-shift Senior i Technical Adviser quall;ications of Section 6.3.1 Reactor Operator only !

• • • • Requirements for minimum number of licensed operators on shift during operation 10CFR50.54(m). in modes other than cold shutdown or refueling are contained in Amendment No:pf,p(,79$ p[ 95

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' ADMINISTRATIVE CONTROLS ~

2 SAFETY LIMIT VIOI.ATION (Continuedi '

b.

The NRC Corporation Center shall be notified by telephone as'socn as possible and in all cases within one hour.

The Vice President Nuclear Operations and de NRB shall be notliled within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

' . c. '

A Safety Limit Violation Report shall be prepared. The report shau be revlewed by the PORC. This report shall describe (D appilcable circumstances preceding the violation, (2) effects of the violation

, upon facility action taken components, to prevent recurrence. systems or ' structures, and (3) corrective d.

The Safety Limit Violation Report shall be ' submitted to the Commission, within 14 days the NRB of the and the Vice Presdient Nuclear Operations violations.

6.8 PROCEDURES 6.S .1 covering theWritten procedures referencedshall be established, implemented and mainta!ned '

activities below a.

The applicable procedures recommended 'In Appendix "A" of

.- Regulatory Guide 1.33, February,1978 ..

1

b. Refueling operations. I c.

Surveillance activities of safety related equipment,

d. Security Plan implementation.

e. Emergency Plan Implementation

f. Fire Protection Program implementathen.

6.8.2 thereto, shall be reviewed by the k' ORC /SORC, as app the' Unit Superintendent / Station Superintendent prior to implementation and revlewed periodically as set forth in eac '; document.

Amendment No.,14, 38', A4', 56, .85', 95 6-16

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'A UNITED STATES y 3I ' NUCLEAR REGULATORY COMMISSION wAssructou. o. c. rosss

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NORTHEAST NUCLEAR ENERGY COMPANY  !

_THE CONNECTICUT LIGHT AND P0_WER COMPANY IfESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 MILLSTONE NOCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.' 92 License No. DPR-65

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-1. The fluelear Regulatory Conmission (the Commissien) has found that:

A. The application for amendment b Ccmpany, et al. (the licensee) ydated the Northeast Nuclearcomplies October 4,1983 Energy with 1954,the standards es anended (theand Act ,req)uirements and the Commis'sion's of therules Atemic and Energy Act of regulations set forth in 10 CFR Chapter I; B.

The fccility will'eperate in conformity with the application, the ~!

provisions Comission; of the Act, and the rules and regulations of the  ;

C.

There is reasonable assurance (i) that the activities authorized by the amendment can be conducted without endangering the health c.nd safety of the public; end (11) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be ininical to the common defense and and security or to the health and safety of the public; E.

The issuar.co of this amendnent is in acccrdance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satir.fied.

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2. Accordingly, the ifcense is enended by changes to the Technical-Specifications as indicated-in the attachment to this licerse amendnent end Paragraph 2.C(2) of Facility Operating License flo.-DPR-65 is hereby amended to read as fellows:

(2)' Technical Set;1fications The Technical Specifications contained in Appendices A and B es revised through Amendment No. 92, 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 its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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James R, Miller, Chief-Operatint Reactors Branch #3 Division;of Licensing

Attachment:

.' Chan;es to the Technical Specifications Date of Issuence: February 16,, 1984 l

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ATTALHMENT TO LICENSE AMEND!ENT NO. 9 2 PROVISIONAL ,0PERATING LICENSE NO. OPR AND -

1.ICENSE A!4ENDMENT NO. --

FACILITY OPERATING LICENSE NO. OPR-65 L _ DOCKET NOS. 50-245/336 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages The revised pages include the creathe ceptioned amendment numbers and marginal lines indicating of change.

Unit 1: Papeg 6-1 6-4 '

6-16 Unit 2: Ron*

.' 6-1 '

6-4 6-16 Ovedeaf cer.pleteness.pagts 6-?, 6-3, and 6-15 are included for maintainico docurent

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C 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Statien Superintendent shall be responsible for overall operation of for operationStation the Millstone Site while the Unit Superintendent shall'be responsible of the unit.

The Station Superintendent and Unit Superintendent shall each delegate in writing the succession to these responsibilities during their absence.

6.2 ORGANIZATION OFFSITE 6.2.1  !

shall be as shown on Figure 6.2-1.The offsite organization for facility managem M ITY STAFF 6.2.2 The' Facility organization shall be as shown on Figure 6.2-2 and:

a.

Each on daty shift shall be composed of at least the rainimum shift crew composition shewn 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 from reactor start-up, scheduled reactor shutdown and during recovery trips.

d. An individual qualified in radiation on site when fuel is in the reactor.# protection procedures shall be

, e.

All CORE ALTERATIONS after the initial fuel loading shall be directly sucervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

A allsite Fire Brigade of at least 5 members shall be maintained onsite at times.#

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.

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 qualifications of ANSIEach member of the facility staff t, hell meet or exceed the mi 1418.1-1971 Radiation Protection Manager.who shall . meet or exceed the qua Regulatory Guide 1.8, Revision 1, and (2) the Shift Technical Advisor who shall l have a Bachelor Degree or equivalent in a scientific or engineering discipline with specific and for transients training in plant design and response and analysis of the plant accidents.

i See Note on Page 6-4.

i-DILLS 70i! - Uld7 2 6-1 Amendment No. is, E6, 78, 9?

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.$AFETY LIMIT VIOLATION (Continued) b.

- The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President i

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

c.

I A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility c.omponents, systems or structures, and (3) corrective action taken to prevent recurrence. i 1

d.

L The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice President Nuclear Operations within 14 days of the violations.

6.8 PROCEDURES 6.8.1 k'ritten procedures shall be established, implemented and maintained 3 . covering the activities referenced below:

..- a. The applicable procedures recommended TN Appendix "A" of

. Regulatory Guide 1.33, February 1978.

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b. Refueling operations.

c. Surveillance activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation. '

f. Fire Protection Program implementation.

I 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC/SORC, as applicable, and approved by the Unit Superintendent / station Superintendent prior to implementation and reviewed periodically as set forth in each document.

,P.!LLSTONE - Utili 2 6-16 Amendment No. 28, 25, 45, 78, 92

i& JAN 22 '88 13:25 NRC MILLSTONE OFFICE P02 l' -

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L TABLE 6.2-i*** l MINIMUM SHIFT CREW C014POSITI0rd - APPLICABLE MODES LICENSE CATEGORY 1, 2, 3 & 4 5&6 SOL 2 1* l OL 2 1 l Non-Licensed 2 1 Shift Technical Advisor ** 1 None i Required

• Coes not include the licensed Senior Reactor or Senior Reactor Operator Limited to fuel Handling individual supervision CORE ALTERATIONS after the initial fuel loading.

                  ! The abcVe shift crew composition and the qualifi'ed health physics technician and/or fire brigade members of Section 6.2.2. may be less than the minimum requirements for a period of time not to exceed 2 hours in order to accomm date unexpected absence provided expeditious actions are taken to fill the required positions.
                  ** The Shift Technical Advisor position may be filled by an on-shift Senior Reactor Operator only if that on-shift Senior Reactor Operator meets the Shift Technical Advisor qualifications of Section 6.3.1.
                  *** Requirements for minimum number of licensed operators on.shif t during oper-ation in modes other than cold shutdown or refueling are contained in 10CFR50.54(m).

MILLSTONE - UNIT 2 6-4 Amendment No. $5, /S, 92 a

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g' , ADjiluiSTRATIyE CONTROL 5 __ AUTHORITY- . 6.5.4.9 The'SNRB report to and advise thE Senior Vice President Nuclear Engineering and Operations on those areas of responsibility specified in Sections 6.5.4.7 and 6.5.4.8. REC 0RDS_ _ 6.5.4.10 Records' of SNRB activities shall be prepared, approved, and distributed as indicated below: ,

a. 141nutes of each SNRB meeting shall be prepared, approved, and forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following each meeting.

b. Reports of reviews enco'taassed by Section 6.5.4.7 abo've shall be prepared, approved, and forwarded to the Senior Vice President Nuclear Engineering and Operations within 14 days following completion of the review.

                  ..           c. Audit reports encompassed by Section 6.5.4.8 above shall be forwarded to the Senior Vice President Nuclear Engineering

.' and Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit. 6 '. 6 REP 0_RTABLE OCCURRENCE ACTION

6. 6.1 The following actions shall be taken for REPORTABLE OCCURRENCES:

a. The Commission shall te notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each REPORTABLE OCCURRENCE Report requiring 24. hour notifica-tion to the Commission shall be reviewed by the PORC and submitted to the NRB and the Vice President Nuclear Ope. rations. l

                ;    6.7 SAFETY LIMIT _ VIOLATION
                !     6 .7.1        The following actions shall be taken in the event a Safety Limit 13 violated:

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

l; MLLSTONE - UuIT 2 6-15 Amendment 30 7 E , ;5. H . '"

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                   'l AD:41N1STRATIVE CONTROLS                            __                                           _

SAFETY LIMIT VIOLATION (Continued)

b. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President Huclear Operations and the NRS shall be notified within 24 hours.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken'to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice President Nuclear Jperations within 14 days of the violations. ,

6.8 PROCEDURES

   ,                . 6.8.1     k'ritten procedures shall be established, $mplemented and maintained

s. covering the activities referenced below:

     .                       a.      The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, February 1978.                                                  l

b. Refueling operations.

c. Surveillance activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

6.8.2 Each procedure and administrative policy of 6.8.1 above, and chances thereto, shall be reviewed by the FORC/SORC, as applicable, and approved by the Unit Superintendent / Station Superintendent prior to implementation and reviewed periodically as set forth in each document. f ti il 11

                 !! MILLSTONE - UNIT 2                        6-16             Amendment No. JE 75, AE, 76, 92
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