ML20245J069

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Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively,modifying Tech Specs of Four Units to Be Consistent W/Plant Restart Provision in 10CFR50.36 If Safety Limit Exceeded
ML20245J069
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 04/25/1989
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245J065 List:
References
NUDOCS 8905030626
Download: ML20245J069 (17)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CONNECTICUT YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-213 HADDAMNECKPLANJ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 114 License No. DPR-61

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

A. The application- for amendment by Connecticut Yankee Atomic Power Company (thelicensee),datedJanuary 12, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 (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 .1111 not be inimical to. the comon 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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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-61 is hereby.

amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.114 , 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 GULATORY COMMISSION

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oh PF. Stolz, Dir c or Pr ject Directorat I-4 vision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 25, 1989 '

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ATTACHMENT TO LICENSE AMENDMENT NO.ll4 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 Insert '

6-13 6-13 a

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. l, Administrative Controls 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for Reportable Events:

a. The Commission shall be notified and/or a report submitted )

pursuant to the requirements of Section 50.73 to 10CFR Part 50 i and

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

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is '

violated.

a. The unit shall be placed in at least HOT STANDBY within one hour.  !
b. The NRC Operations Center shall be notified by telephone as scon as l possible and in all cases within one hour. The Vice Prestdent '

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. 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 Operations within 14 days of the violation.
e. Operation shall not be resumed until authorized by the Commission.

6.8 P_ROCEDVRES 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and '

recommendations of Section 5.1 and 5.3 of ANSI N18.7-1976 and Appendix "A" of USAEC Regulatory Guide 1.33 except as provided in 6.8.2 and 6.8.3 below. I Procedures shall be established and maintained for implementation of the Facility Fire Protection Program.  ?

6.8.2 Each proc 2 dure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PORC and approved by the Station

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

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6-13 Amendment No. 114 l

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NORTHEAST NUCLEAR ENERGY COMPANY 1

DOCKET NO. 50-245 MILLSTONE Nt! CLEAR POWER STATION, UNIT NO. 1  !

AMENDMENT TO FACILITY OPERATING LICENSE _

Amendment No. 30 License No. DPR-21

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

A. . The application for amendment by Northeast Nuclear inergy Company (thelicensee),datedJanuary 12, 1989 complies with the standards and requirements of the Atemic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission's regulations; D. The issuance of this amendment will not be inimical to the co m on 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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_.__..m_.______.__________m______

2. Accredingly, the license is amended by changes to the Technical Spe'ifications 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. 30 , 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.

F THE NUCLEAR RE LATORY COMMISSION .c

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J n F. Stolz. Direc$gr roj ct Directorate E-4 sion of Reactor Projects'I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 25, 1989 I

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___________.____.__.__________m_.__.___-

ATTACHMENT TO LICENSE AMENDMENT NO.30 FACILITY OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages'as indicated . The revised pages are identified by amendment number and contains a vertical line indicating the areas of. change.

Remove Insert 6-16 6-16 1

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ADMINISTRATIVE CONTROLS

d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB, and the Vice President Nuclear Operations within 14 days of the violation.
e. Operation shall not be resumed until authorized by the Commission.

6.8 PROCEDURES l 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below.

a. The applicable procedures recommended in Appendix "A" of Regulatory I Guide 1.33, February, 1978.
b. Refueling operations. I
c. Surveillance activities of safety related equipment.
d. Security Plan implementation I
e. Emergency Plan Implementation
f. Fire Protection Program Implementation
g. Quali+y Control for effluent monitoring using the guidance in Regulatory Guide 1.21 Rev.1, June 1974. I
h. Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 00CM) implementation, except for Section I.E.,

Radiological Environmental Monitoring.

6.8.2 Each procedure and administrative policy o" 6.8.1 above, and changes thereto, shall be reviewed by che PORC/SORC, as appli- i cable, and approved by the Unit Superintendent / Station Superin- '

tendent prior to implementation and reviewed periodically as set forth in each document.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of original procedure is not altered,
b. The change is approved by two members of the plant management i staff, at least one of whom holds a Senior Reactor Operator's j License on the unit affected. [
c. The change is documented, reviewed by the PORC/SORC, as I applicable, and approved by the Unit Superintendent / Station Superintendent within 14 days of implementation.  !

1 6.8.4 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REM 0DCM.

l Millstone Unit 1 6-16 Amendment No, 30 1

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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY l DOCKET NO. 50-336 l MILLSTONE NUCLAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE j

. Amendment No.141 j License No. DPR-65 :

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

A. The application for amendment by Northeast Nuclear Energy Company, etal.(thelicensee),datedJanuary 12, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; l B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l 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 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-65 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.141, are hereby incorporated in the license.

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

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

FOR THE NUCLEAR REG LATORY COMMISSION J 'F. Stolz, Dire t r P o ect Directorate -4 ision of Reactor Projects I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 25, 1989 I

ATTACHMENT TO LICENSE AMENDMENT NO. 141 FACILITY OPERATING LICENSE NO. DPR 65 DOCKET NO. 50-336' Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contains a vertical line indicating the areas of change.

Remove Insert 6-16 6-16 n

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.* j ADMINISTRATIVE CONTROLS .-. .

SAFETY LIMIT VIOLATION (Continued)

b. The NRC Corporation Center shall se notified by telephone as soon as possible and in all cases within one hour. The Vice President 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. A Safety Limit Violation Report s1all 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 j upon facility components, systems or structures, and (3) corrective i action taken to prevent recurrence.  !

d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice Presdient Nuclear Operations within 14 days of the violations.
e. Operation shall not be resumed until authorized by the Commission. -I 6.8 PROCEDVRES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:

)

a. The applicable procedures recomm-anded in Appendix "A" of Regulatory Guide 1.33, February, 1978.
b. Refueling operations.
c. Surveillance activities of safety related equipment. ,
d. Security Plan implementation.
e. Emergency Plan implementation
f. Fire Protection Program implement ation.
g. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev.1, Ane 1974.
h. Radiological Effluent Monitoring _ and Offsite Dose Calculation Manual (REMODCM) implementation except for Section I.E. Radiological Environmental Monitoring.

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 l reviewed periodically as set forth in each document.

MILLSTONE - UNIT 2 6-16 Amendment No. 141

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NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.*

DOCKET NO. 50-423 i

MILLSTONE NUCLAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE

. Amendment No. 33 License No. NPF-49

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

A. The application for amendment by Northeast Nuclear Energy Corupany, etal.(thelicensee),datedJanuary 12, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity vith 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 1 been satisfied.

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  • Northeast Nuclear Energy Company is authorized to act as agent and represent -

ative for the following Owners: Central Maine Power Company, Central Vemont j Public Service Corporation, Chicopee Municipal Lighting Plant, City of  ;

Burlington, Vermont, Connecticut Municipal Electric Light Company, l Massachusetts Municipal Wholesale Electric Company, Montaup Electric Company, l New England Power Company, The Village of Lyndonville Electric Department, j

( Western Massachusetts Electric Company, and Vemont Electric Generation and "

1 Transmission Cooperative, Inc., and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

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2. Accordingly, the license is amended by changer to the Technical 1 Specifications as. indicated in the attachment ta this license amendment, and paragraph 2.0.(2) of Facility Operating License'No. NPF-49 is hereby j amended to read as follows. 3 (2) Technical Specifications i 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.

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3. This license amendment is effective as of the date of issuance, to be 1 implemented wit'iin 30 days of issuance.

F R THE NUCLEAR R GULATORY COMMISSION r

~

1 i Jh F. Stolz, Direp:or ro ect Directorate)I-4 ision of Reactor Projects I/II Office of Nuclear Reactor Regulation ]

Attachment:

Changes to the Technical -l Specifications Dcte of Issuance: April 25, 1989 1

j

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4 ATTACHMENT TO LICENSE AMENDMENT NO. 33 FACILITY OPERATING LICENSE NO. NPF-49 I l

DOCKET NO. 50-423 i Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by )

amendment number and contains a vertical line indicating the areas of change. j Remove Insert 6-12 6-12 6-16 6-16 b

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@MINISTRATIVE CONTR0l.S REVIEW 6.5.3.6 The NRB shall function as an independent review body and shall review:

a. The safety evaluations for: (1) changes to procedures, equipment, or systems; and (2) tests or experiments completed under the i provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question;
b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59;
c. Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; I
d. Proposed changes in Sections 1.0-5.0 of these Technical Specifications or this Operating License; '

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e. Violations of Codes, regulations, orders, Technical ,

Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance; l i

f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety;
g. All REPORTABLE EVENTS;
h. Indications of a significant unanticipated deficiency, affecting nuclear safety, in some aspect of design or operation of structures, systems, or components; and
1. Reports and meeting minutes of the PORC.

AUDITS 6.5.3.7 Audits of unit activities shall be performed under the cognizance

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of the NRB. These audits shall encompass:

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a. The conformance of unit operation to provisions contained within i the Technical Specifications and applicable license conditions at l least once per 12 months;
b. The performance, training, and qualifications of the unit staff at least once per 12 months; .

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c. The results of actions taken to correct deficiencies occurring in l unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; and
d. Any other area of unit operation considered appropriate by the NRB or the Senior Vice President-Nuclear Engineering and Operations.

I MILLSTONE - UNIT 3 6-12 Amendment No. 33

ADMINISTRATIVE CONTROLS i

SAFETY LIMIT VIOLATION (Continuec)

d. The Safety Limit Violation ' Report shall be. submitted to the Commission, the Chairman of the NRB, .and the. Vice i President-Nuclear Operations within 14 days of the violation;'and '
e. Operation shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix A' of Regulatory

, Guide 1.33, Revision 2, February 1978;

b. The applicable procedures required to implement the require-ments of NUREG-0737 and supplements thereto;
c. Refueling operations;
d. Surveillance activities of safety related equipment;
e. Security Plan implementation; l
f. Emergency Plan implementation; J
g. Fire Protection Program implementation;
h. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974; and
1. Radiological Effluent Monitoring and. Offsite Dose Calculation Manual (REMODCM) implementation except for Section I.E, Radiological- Environmental' Monitoring.

6.8.2 Each procedure of Specification 6.8.1, and changes. thereto, shall be reviewed by the PORC/SORC, as appropriate, and shall be approved by the Unit Superintendent / Station Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made pro--

vided:

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 j MILLSTONE - UNIT 3 6-16 Amendment No. 33 .;

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