ML20073P823
| ML20073P823 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/09/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073P825 | List: |
| References | |
| NUDOCS 9105230154 | |
| Download: ML20073P823 (12) | |
Text
..
m s%
UNITED STATES
-[
NUCLEAR REGULATORY COMMISSION g
W ASHINGTON, D, C. 20555 k
- e,s e
- NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 96 License No. DPR-42 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated January 30, 1991,-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 regule+1ons of the Comission; C.
Thereis.reasonableassurance(i)thattheactivitiescuthorized by this amendment can be conducted without endangering the health-and safety of the public, and (ii) that such activities i
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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have l
been st,tisfied.
L 2.
Accordingly, the license is amended by changes.to the Technical Specifica-tions'as.. indicated in the attachment to.this license amendment, and para-graph 2.C.(2) of Facility Operating License No._ DPR-42 -is hereby amended to-read as follows:
l p!85"$0$$ Noohg2 P
. _... _ ~. _, _ _..
_. _, _. - ~,. _. _ _
... _ - _ _ _. _. _.. ~. _.,.. _ _. _ _.. _ -
e 2
Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No.96, are hereby incorporated in the license The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 9, 1991 l
l i
i l
l l
- .94
- 0 UNITED STATES
,og 8
NUCLEAR REGULATORY COMMISSION a
5
- l W ASHING TON, D. C, 20555
\\,
/
e...+
NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-60 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated January 30, 1991, 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 Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission'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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
I
l 2
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.89, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 9, 1991 a
s' ATTACHMENT TO LICENSE AMENDMENT NO. 46 TACILITY OPERATING LICENSF NO. DPR-42 DOCKET NO. 50-282 Revise Appendix A Technical 5)ecifications by removing the pages identified below and inserting the attacled pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT TS-viii TS-viii TS.6.2-6 TS.6.2-6 15.6.2-7 TS.6.2 7 L
s' TS.viii TABLE OF CONTENTS (Continued)
TS SECi..;j TITLE PACE 6.0 ADMINISTRATIVE C0tiTROLS TS.6.1 1 6.1 Organization TS.6.1 1 6.2 Review and Audit TS 6.2 1 A. Safety Audit Committee (SAC)
TS.6.2 1
- 1. Membership TS.6.2 1
- 2. Qualifications TS.6.2 1
- 3. Meeting Frequency TS.6.2 2
- 4. Quorum TS.6.2 2
- 5. Responsibilities TS.6.2 2
- 6. Audit TS.6.2 3
- 7. Authority TS.6.2 4
- 8. Records TS 6.2 4
- 9. Procedures TS.6.2 4 B. Operations Committee (OC)
TS.6.2 5
- 1. Membership TS.6.2 5
- 2. Meeting Frequency T5.6.2 5
- 3. Quorum TS 6.2 5
- 4. Responsibilities TS 6.2 5 t
- 5. Authority TS.6.2 6
- 6. Records 75.6.2 6
- 7. Procedures TS.6.2 6 C. Maintenance Procedu'.es TS 6.2 7 l
6.3 Special Inspections and Audits TS 6.3 1 6.4 Safety Limit Violatior.
TS.6.4 1 6.5 Plant Operating Procedures TS.6.5 1 A. Plant Operatie,ns TS.6.5 1 B. Radiological, TS.6.5 1 C. Maintenance and Test TS.6.5 3 D. Process Control Trogram (PCP)
TS.6.5 3 E. Offsite Dose Calculation Manual (ODCM)
TS 6.5 4 F. Securtiy TS.6.5 4 G. Temporary Changes to Procedures TS.6.5 4 6.6 Plant Operating Records TS.6.6 1 A. Records Retained for Five Years TS 6.6 1 B. Records Retained for the Life of the Plant TS.6.6 1 1
Prairie Island Unit 1 - Amendment No. AS,13 f.0, 9f, 96 Prairie Island Unit 2 - Amendment flo. AD, $6. 73, Jg(. 89 I
TS 6.2 6 f.
Investigations of all Reportable Events and events requiring Special Peports to the Commission, g.
Drills on emergency procedures (including plant evacuation) and adequacy of communication with offsite support groups, h.
All procedures required by these Technical Specifications, including implementin6 procedures of the Emergency Plan, and the Security Plan (except as exempted in Section 6.5.F), shall be reviewed initially and periodically with a frequency commensurate with their safety significance but at an interval of not more than two years. Maintenance work requests and their associated procedures shall be reviewed per the requirements of Section 6.2.C.
i.
Special reviews and investigations, as requested by the Safety Audit Committee.
j.
Rsview of investigative reports of unplanned releases of radioactive material to the environs.
k.
All changes to tae Process Control Program (PCP) and the Offsite Done Calculation Manual (CDCM).
1.
The review of safety evaluations, when safety evaluations are required by 10 CTR Part 50 Sert n 50.59, for procedures or procedure changes to verify that such actions do not constitute an unreviewed safety questior 5.
Authority The OC shall be advisory to the Plant Manager.
In the event of a disagreement betueen the recommendations of the OC and the Plant
- iger, the co"rse determined by the Plant Manager to be the more nservative vill be followed. A vritten summ ry of the disagreement will be sent to the General Manager Nuclear Plar.ts and the Chairman of the SAC for review.
6.
Records Minutes shall be recorded for all meetings of the OC and shall identify all documentary material reviewed.
The minutes shall be distributed to each member of the OC, the Chairman and each member of the Safety Audit Committee, the General Manager Nuclear Plants and others designated by the OC Chairman or Vice Chairman.
7.
Procedures A written charter for the Oc shall be prepared that contains:
Responsibility and authority of the group a.
Prairie Island Unit 1 - Amendment No. /3.59./3.86, 96 Prairie Island Unit _2 - Amendment No. 13.53.56.ff,89
TS.6.2 7 b.
Content and method of submission of presentations to the Operations Committee c.
Mechanism for scheduling meetings d.
Provision for meeting agenda C.
Maintenance Procedures 1.
Maintenance work requests and their associated procedures required by specification 6.5.C and changes thereto, shall be prepared, reviewed and approved.
Each procedure or procedure change shall be reviewed by a qualified individual (s) other than the individual (s) who prepared the procedure or procedure change.
The appropriate superintendent (as previously designated by the Plant Manager) shall approve these procedures.
2.
Individuals responsible for rev.ews performed in accordance with the requirements of specification 6.2.C.1 above shall meet or exceed the qualifications described in section 4.2 or 4.4 of ANSI N10.1 1971 and shall be previously designated by the Plant Manager.
Such reviews shall include a determination of whether or not additional cross disciplinary review is necessary.
3.
All reviews shall include a determination of the need for a safety evaluation to establish whether or not an unreviewed safety question is involved.
Prairic Island Unit 1 - Amendment ho. 96 Prairie Island Unit 2 - Amendment No. 89 I
ATTACHMENT TO LICENSE AMENDMENT NO. 89
-FACILITY OPERATING LICEliSE NO. OPR-60 DOCKET NO. 50-306 Revise Appendix A Technical $)ecifications by removing the pages identified below and-inserting the attacled pages.
The revised pages are identified by amendment nunber and contain marginal lines indicating the area of change.
REMOVE INSERT TS-viii TS-viii TS.6.2-6 TS.6.2 6 TS 6.2-7 TS 6.2-7 4
l
t T3 viii TABLE OF CONTENTS (Continued)
TS SECTION TITLE PACE 6.0 ADMINISTRATIVE CONTROLS TS.6.1 1 6.1 Organization TS.6.1 1 6.2 Review and Audit TS.6.2 1 A. Safety Audit Committee (SAC)
TS.6.2 1
- 1. Membership TS.6.2 1
- 2. Qualifications TS.6.2 1
- 3. Meeting Frequency TS.6.2 2
- 4. Quorum TS.6.2 2
- 5. Responsibilities TS.6.2 2
- 6. Audit TS.6.2 3
- 7. Authority TS.6.2 4
- 8. Records TS.6.2 4
- 9. Procedures TS.6.2 4 B. Operations Committee (OC)
TS.6.2 5
- 1. Membership 75.6.2 5
- 2. Meeting Frequency TS.6.2 5
- 3. Quorum TS.6.2 5
- 4. Responsibilities TS.6.2 5
- 5. Authority TS.6.2 6
- 6. Records TS.6.2 6
- 7. Procedures TS.6.2 6 C. Maintenance Procedures 75.6.2 7 l
w 6.3 Special Inspections and Audits T5.6.3 1 6.4 Safety Limit Violation TS.6.4 1 6.5 Plant Operating Procedures TS.6.5 1 A. Plant Operations TS.6.5 1 B. Radiological TS.6.5 1 C. Maintenance and Test TS.6.5 3 D. Process Control Program (PCP) 75.6.5 3 E. Vffsite Dose Calculation Manual (ODCM)
TS 6.5 4 F. Securtiy TS.6.5 4 G. Temporary Changes to Procedures TS.6.5 4 6.6 Plant Operating Records TS.6.6 1 A. Records Retained for Five Years TS.6.6 1 B. Records Rotained for the Life of the Plant TS.6.6 1 Prairie Island Unit 1 - Anendment No. AB, 73. E0, 9I, 96 Prairie Island Unit 2 - Amendment No. 10, 66, 73, 84, 89
TS.6.2 6 f.
Investigations of all Reportable Events and events requiring Special Reports to the Commission, g.
Drills on emergency procedures (including plant evacuation) and adequacy of communication with offsite support groups.
h.
All procedures required by these Technical Specifications, including implementing procedures of the Emergency Plan, and the Security Plan (except as exempted in Section 6.5.F), shall be reviewed initially and periodically with a frequency commensurate with their safety signifit.nce but at an interval of not more than two years.
Maintenance work requests and their associated procedures shall be reviewed per the requirements of Section 6.2.C.
i.
Special reviews and investigations, as requested by the Safety Audit Committee.
- j. Review of investigative reports of unplanned releases of radioactive materini to the environs.
k.
All changes to the Process Control Program (PCP) and the Offsite Dose Calculation Manual (ODCM).
1.
The review of safety evaluations, when safety evaluations are required by 10 CFR Part 50, Section 50.59, for procedures or procedure changes to verify that such actions do not constitute an unreviewed safety question.
5.
Authority The OC shall be advisory to the Plant Manager.
In the event of a disagreement between the recommendations of the OC and the Plant Manager, the course determined by the Plant Manager to be the more conservative vill be followed. A written summary of the disagreement will be sent to the General Manager Nuclear Plants and the Chairman of the SAC for review.
6.
Records Minutes shall be rscorded for all meetings of the OC and shall identify all documentary material reviewed. The minutes shall be distributed to each member of the OC, the Chairman and each member of the Safety Audit Committee, the General Manager Nuclear Plants and others designated by the OC Chairman or Vice Chairman.
7.
Procedures A written charter for the OC shall be prepared that contains:
a.
Responsibility and authority of the group Prairie Island Unit 1 - Amendment No. 49.59.73.86, 96 Prairie Island Unit 2 - Amendment No. g),53,EE,73, 89
s'
\\
TS.6.2 7 b.
Content and method of submission of presentations to the Operations Committee c.
Mechanism for scheduling meetings d.
Provision for meeting agenda C.
Maintenance Procedures 1.
Maintenance work requests and thdir associated procedures required by specification 6.5.C and changes thereto, shall be prepared, reviewed and approved.
Each procedure or procedure change shall be reviewed by a qualified individual (s) other than the individual (s) who prepared the procedure or procedure change.
The appropriate superintendent (as previously designated by the Plant Manager) shall approve these procedures.
2.
Individuals responsible for reviews performed in accordance with the requirements of specification 6.2.C.1 above shall meet or exceed the qualifications described in section 4.2 or 4.4 of ANSI N18.1 1971 and shall be previously designated by the Plant Manager.
Such reviews shall include a determination of whether or not additional cross disciplinary review is necessary.
3.
All reviews shall include a determination of the need for a safety evaluation to establish whether or not an unreviewed safety question is involved.
Prairie Island Unit 1 - Amendment No. 96 Prairie Island Unit 2 - Amendment No. 89 1
_ - _ _ _ - - _ _ _ _ _ _ - _ - _ _ - _ _ _ _ _ _ - _ _ _ - _ - _ - _ _ - _ - _- - - - - - - _ - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -