ML20044D312
| ML20044D312 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/04/1993 |
| From: | Bill Dean Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044D314 | List: |
| References | |
| NUDOCS 9305180486 | |
| Download: ML20044D312 (36) | |
Text
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UNITED STATES
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flMi j NUCLEAR REGULATORY COMMISSION
- g WASHINGTON D.C. 20555-0001 s,
NORTHERN STATES POWER COMPANY DOCKET NO. 50-282 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 105 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 l
licensee) dated February 25, 1991 as revised February 22, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and i
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 Commission's regulations; 4
D.
The issuance of this amendment will not be inimical to the common i
defense and security or to the health and safety of the public; and E.
The issue.nce 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-42 is hereby amended to read as follows:
9305180486 930504 PDR ADOCK 05000282 P
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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.105, 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.
I FOR THE NUCLEAR REGULATORY COMMISSION I
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William M. Dean, Acting Director Project Directorate III-l Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
Pey 4,1993 i
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ATTACHMENT TO LICENSE AMENDMENT NO.105 FACILITY OPERATING LICENSE NO. DPR-42 f
DOCKET NO. 50-282 f
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by l
amendment number and contain vertical lines indicating the area of change.
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i REMOVE INSERT TS-xiii TS-xiii TS.6.1-1 TS.6.1-1 TS.6.1-2 TS.6.1-2 TS.6.1-3 TS.6.1-3 TS.6.1-4
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Table TS.6.1-1 Table TS.6.1-1 Figure.TS.6.1-1 Figure TS.6.1-2 i
TS.6.2-1 TS.6.2-1 TS.6.2-3 TS.6.2-3 TS.6.2-4 TS.6.2-4 TS.6.2-5 TS.6.2-5 l
TS.6.2-6 TS.6.2-6 TS.6.4-1 TS.6.4-1 2
TS.6.5-4 TS.6.5-4 TS.6.7-5 TS.6.7-5 l
TS.6.7-6 TS.6.7-6 l
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o TS-xiii APPENDIX A TECHNICAL SPECITICATIONS LIST OF FIGURES TS FIGURE TITLE 2.1-1 Safety Limits, Reactor Core, Thermal and Hydraulic Two Loop Operation 3.1-1 Unit 1 and Unit 2 Reactor Coolant System Heatup Limitations 3.1-2 Unit 1 and Unit 2 Reactor Coolant System Cooldown Limitations 3.1-3 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL PO'.'.ER with the Primary Coolant Specific Activity >1.0 uCi/ gram DOSE EQUIVALEhI I-131 3.9-1 Prairie Island Nuclear Generating Plant Site Boundary for Liquid Effluents 3.9-2 Prairie Island Nuclear Generating Plant Site Boundary for Caseous Effluents 3.10-1 Required Shutdown Margin Vs Reactor Boron Concentration 4.4-1 Shield Building Design In-Leakage Rate Prairie Island thit 1 - kentent te. Pf, 92,106 Prairie Island thit 2 - kentent tb. 8#, 85, 93
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TS.6.1-1 6.0 ADMINISTPATIVE CONTROLS 6.1 Organization A.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities i
necessary for safe operation and maintenance of the plant. The Plant Manager shall delegate in writing the succession to this
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responsibility during his absence. The Plant Manager has the responsibility for the Fire Protection Program i
B.
Onsite and Offsite Organizations Onsite and offsite organizations shall be established for plant I
operation and corporate management. The onsite and offsite organizations shall include the positions responsible for
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activities affecting plant safety.
- 1. 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 for= 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 Operational Quality Assurance Plan or the Updated Safety Analysis Report.
- 2. There shall be an individual executive position (Vice President
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Nuclear Generation) in the offsite organization having corporate t
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.
- 3. There shall be an individual management position (Plant Manager) in the onsite organization having responsibility for overall unit safe operation and who shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
- 4. 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.
j C.
Plant Staff:
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- 1. Each on duty shift shall be composed of at least the minimum shift crew composition shown on Table TS.6.1-1.
- 2. For each reactor that contains fuel: a licensed operator in the control room.
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TS.6.1-2 3.
At least two licensed operators shall be present in the control room during a reactor startup, a scheduled reactor shutdown, and during recovery from a reactor trip. These operators are in addition to those required for the other reactor.
4 An individual qualified in radiation protection procedures shall be on site when fuel is in a reactor.
5.
All refueling operations shall be directly supervised by a licensed Senior Reactor Operator or a Senior Reactor Operator Limited to Puel Handling who has no other concurrent respons-ibilities during this operation.
6.
A fire brigade of at least five members shall he naintained on site at all times.* The fire brigade shall not include the six nembers of the minimum shift crew for safe shutdown of the reactors.
7.
The General Superintendent Plant Operations shall be formerly licensed or hold a current license on a similar type plant.
8.
At least one nember of plant management holding a current Senior Reactor Operator license shall be assigned to the plant operations group on a long tern basis (approximately two years). This individual shall not be assigned to a rotating shift.
D.
Each nember of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the General Superintendent Radiation Protection who shall meet or l
exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Manager who shall have a bachelors degree or equivalent in a l
scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents, and (3) the General Superintendent Plant Operations who shall neet the requirements of ANSI N18.1-1971, except that NRC license requirements are as specified in Specification 6.1.C.7.
The training l
program shall be under the direction of a designated nenber of Northern States Power management.
' Tire Erigade cosposition may be less than the ninimum requirements for a period of tine 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 of Fire Brigade sembers provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.
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TS.6.1-3 E.
A training progra: for the fire brigade shall be maintained under the direction of a designated cember of Northern States Power canagement.
t This program shall ceet the requirements of Section 27 of the NFPA Code -
J 1976 with the exception of training scheduling. Fire brigade training j
shall be scheduled as set forth in the training program.
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F.
Ad=inistrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g.,
J senior reactor operators, reactor operators, health physicists, auxiliary 1
operators, and key caintenance personnel.
Proadures shall include the t
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following provisions:
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1.
Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel l
work a nominal 40-hour week while the plant is operating. However, in l
i the event that unforeseen problems require substantial amounts of overtice to be used, or during extended periods of shutdown for refueling. najor caintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
- a. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight excluding shift turnover ti=e.
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- b. CNertime should be limited for all nuclear plant staff personnel so i
that total work time does not exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, l
nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> in l
any seven day period, all excluding shift turnover time.
Individ als should not be required to work more than 15 consecutive days without l
two consecutive days off.
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c.
A break of at least eight hours including shift turnover time should be allowed between vark periods.
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d.
Except during extended shutdown periods, the use of overtice should j
be considered on an individual basis and not for the entire staff on l
J a shift.
j e.
Shift Emergency Coordinator (SEC) on-site rest time periods shall l
j not be considered as hours worked when deternining the total work j
time for which the above limitations apply.
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2.
Any deviation from the above guidelines shall be authorized by the Plant Manager or designee, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
During plant energencies, the Energency Director shall have this authority. Controls shall be included in the procedures such that individual overtine shall be reviewed conthly to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not allowed.
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1 TABLE TS.6,1-1 WW ky-MINIMUM SilIFT CREW COMI'OSITION (Note 1 and 3)
FF EE g-db CATEGORY BOTil UNITS IN Col.D SliUTDOWN ONE UNIT IN COLD SliUTDOWN BOTil UNITS ABOVE COLD E[
OR REFUELING SilUTDOWN OR REFUELING SIIUTDOWN AND SilUTDOWN
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ONE UNIT ABOVE COLD SilUTDOWN ro m No. Licensed Senior 2 (Note 2) 2-(Notes 2, 4) 2 (Note 4)
Operators (LS0)
Total No. Licensed 4
4 5
gg Operators (LSO 6.LO)
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Total No. Licensed 6 6
7 8
L Unlicensed Operators i
Blb Shift Manager (Note 5) 0 1
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8 NOTES:
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1.
Shift crew composition may be one less than the ' minimum requirements for a period of time not to exceed two hours in order to accommodate an unexpected absence of one duty shift crew member provided immediate action is taken to restore the shift crew composition to within the minimum requirements specified.
2.
Does not include the licensed Senior Reactor Operator, or Senior Reactor Operator Limited to Fuel Handling, supervisin6 refueling operations.
.t 3.
Each LSO and ID shall be licensed on each unit.
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One LSO shall be in the control room at all times when a reactor is above cold shutdown.
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5.
'Ihe Shift Manager performs the functions of the Shif t Technical Advisor l$."r.
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TS.6.2-1 6.2 Review and Audit Organizational units for the review and audit of facility operations shall be constituted and have the responsibilities and authorities outlined below:
A.
Safety Audit Committee (SAC) i The Safety Audit Co==ittee provides the independent review of plant operations from a nuclear safety standpoint. Audits of plant operation are conducted under the cognizance of the SAC.
1.
Membership The SAC shall consist of at least five (5) persona.
a.
b.
The SAC chairman shall be an NSP representative, not having line responsibility for plant operation, appointed by the corporate officer. Other SAC ne=bers shall be appointed by the corporate officer or by such other person as he may designate.
The Chairnan shall appoint a Vice Chairman from the SAC nechership to act in his absence.
No more than two ne=bers of the SAC shall be from groups c.
holding line responsibility for operation of the plant.
d.
A SAC nenber may appoint an alternate to serve in his absence, with concurrence of the Chairman. No more than one alternate shall serve on the SAC at any one time. The i
alternate neeber shall have voting rights.
2.
Qualifications The SAC nesbers should collectively have the capability a.
required to review activities in the following areas:
nuclear power plant operations, nuclear engineering, chemistry and radiochenistry, netallurgy, instrumentation and control, radiological safety, nachanical and electrical i
engineering, quality assurance practices, and other appro-priate fields associated with the unique characteristics of the nuclear power plant.
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f.
Investigation of all Reportable Events and events requiring Special Reports to the Commission.
l g.
Revisions to the Facility Emergency Plan, Facility Security Plan, and the Fire Protection Program.
j h.
Operations Committee minutes to determine if matters considered by that Committee involve unreviewed or unresolved safety questions.
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Other nuclear safety matters referred to the SAC by the Operations l
Committee, plant management or company management.
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- j. All recognized indications of an unanticipated deficiency in some aspect j
of design or operation of safety related structures systems, or components.
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Reports of special inspections and audits conducted in accordance with
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Specification 6.3.
l 1.
Changes to the Offsite Dose Calculation Manual (ODCM).
Review of investigative reports of unplanned releases of radioactive m.
material to the environs.
6.
Audit - The operation of the nuclear power plant shall be audited formally under the cognizance of the SAC to assure safe facility operation.
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Audits of selected aspects of plant operation, as delineated in Paragraph a.
4.4 of ANSI N18.7-1972, shall be performed with a frequency commensurate with their nuclear safety significance and in a manner to assure that an audit of all nuclear safety related activities is completed within a period of two years. The audits.shall be performed in accordance with_
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appropriate written instructions and procedures.
b.
Audits of aspects of plant radioactive effluent treatment and radio-logical environmental monitoring shall be performed as follows:
2 1
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- 1. Irrplementation of the Offsite Dose Calculation Manual at least once cvery two years.
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- 2. Implementation of the Process Control Program for solidification of l
4 radioactive vastes at least onie every two years.
- 3. The Radiological Environmental Monitoring Program and the results b
thereof, including quality controls, at least once every year.
j c.
Periodic review of the audit program should be performed by the SAC at q
1 east twice a year to assure its adequacy.
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I d.
Written reports of the audits shall be reviewed by the Vice President j
Nuclear Generation, by the SAC at a scheduled meeting, and by members i
of management having responsibility in the areas audited.
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Authority i
The SAC shall be advisory to the Vice President Nuclear Generation.
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8.
Records f
t Minutes shall be prepared and retained for all scheduled neetings of the Safety Audit Committee.
The minutes shall be distributed within one conth of the meeting to the Vice President Nuclear Generation, each l
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= ember of the SAC and others designated by the Chairman. There shall i
be a fornal approval of the minutes.
9.
Procedures A written charter for the SAC shall be prepared that contains:
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a.
Subjects within the purview of the group.
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Responsibility and authority of the group.
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Mechanisms for convenin5 ceetings.
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d.
Provisions for use of specialists or subgroups.
t Authority to obtain access to the nuclear power plant operating e.
record files and operating personnel when assi ned audit functions.
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3 f.
Requirements for distribution of reports and minutes prepared by the group to others in the NSP organization.
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B.
Operations Co=mittee (OC) 1.
Membership The Operations Committee shall consist of at least six (6) regular members drawn from the key supervisors of the onsite staff. The key supervisors include, at least, the following positions: Plant Manager, General Superintendent Plant Operations, General Superintendent Plant Maintenance, General Superintendent Radiation Protection and Chemistry and Plant Engineering Supervisors.
Alternates to the regular nenbers shall be designated in writing by the Chairman to serve on a temporary basis. No more than two alternates shall participate as voting members of the Operations Committee at any one time.
The Plant Manager shall serve as Chairman of the OC and shall j
appoint a regular member to act as Chairman in his absence.
2.
Meeting Frequency The Operations Committee vill ceet on call by the Chairman or requested by individual members and at least conthly.
3.
Quorum A cajority of the sembership, including the Chairman.
4 Responsibilities - The following subjects shall be reviewed by
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the Operations Committee:
Proposed tests and experiments and their results, a.
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- b. Modifications to plant systems or equipment as described in the Updated Safety Analysis Report and having nuclear safety significance or which involve an unreviewed safety question as defined in Paragraph 50.59 (c), Part 50, Title 10, Code of Federal Regulations, j
- c. Proposals which would effect permanent changes to normal and emergency operating procedures and any other proposed 4
changes or procedures that vill affect nuclear safety as j
determined by the Plant Manager.
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- d. Proposed changes to the Technical Specifications or operating licenses.
- e. All reported or suspected violations of Technical Specifica-tions, operating license requirements, administrative procedures, operating procedures. Results of investigations, including evaluation and recommendations to prevent recurrence vill be reported in writing to the Vice President Nucl ar Generation and to the Chairman of the Safety Audit Committee.
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TS.6.2-6 t
f.
InvestiEations of all Reportable Events and events requiring Special Reports to the Commission.
i g.
Drills on energency procedures (including plant evacuation) and adequacy of communication with offsite support groups.
h.
All procedures required by these Technical Specifications, including implenenting procedures of the Energency 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
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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 1
Committee.
- j. Review of investigative reports of unplanned releases of radioactive caterial to the environs.
k.
All changes to the Process Control Progran (PCP) and the Offsite Dose Calculation Manual (CCOM).
1.
The review of safety evaluations, when safety evaluations are required by 10 CFR Part 50, Section 50.59, for procedures or j
procedure changes to verify that such actions do not constitute an unreviewed safety question.
5.
Authority The DC shall be advisory to the Plant Manager.
In the event of a disagreement between the recomsendations of the OC and the Plant l
Manager, the course deter =ined by the Plant Manager to be the nore 2
conservative vill be followed. A vritten summary of the disagree =ent vill be sent to the Vice President Nuclear Generation and the Chairman l
of the SAC for reviev.
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6.
Records l
1 Minutes shall be recorded for all neetings of the OC and shall identify all docu entary saterial reviewed. The cinutes shall be distributed to each nenber of the OC, the Chairman and each nenber of 1
the Safety Audit Co=sittee, the Vice President Nuclear Generation and others designated by the OC Chairman.
7.
Procedures j
A written charter for the OC shall be prepared that contains:
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Responsibility and authority of the group a.
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6.4 SAFETY LIMIT VIOLATION
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If a Safety Limit is exceeded, the reactor shall be shut down and the l
l Commission shall be notified im=ediately.
It shall also be promptly l
reported to the Vice President Nuclear Generation and the Chairman of the.
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Safety Audit Committee, or their designated alternates. A safety limit l
violation report shall be prepared. This report shall describe (1) applicable circu= stances preceding the violation, (2) effects of the l
l violation upon facility components, systems or structures, and (3) the i
basis for corrective action taken to preclude recurrence.
The report i
shall be reviewed by the Operations Com=ittee. The safety limit j
violation report shall be submitted to the Commission, the Vice President i
i Nuclear Generation and the Safety Audit Committee within two weeks of the j
event.
j Operation shall not be resumed until authorized by the Nuclear Regulatory
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Commission.
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TS.6.5-4 E.
Offsite Dose Calculation Manual (ODCM) s The ODCM shall be approved by the Commission prior to initial l
implementation. Changes to the ODCM shall satisfy the following requirements:
1.
Shall be submitted to the Co==ission with the Semi-Annual Radioactive i
Effluent Report for the period in which the change (s) were made effective. This sub=ittal shall contain:
a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information sub=itted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a revision date, together with appropriate analyses or evaluations justifying the change (s).
- b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint detereinations; and i
- c. documentation of the fact that the change has been reviewed and found acceptable by the Operations Com=ittee.
2.
Shall beco e effective upon review and acceptance by the Operations Co==ittee.
J F.
Security 4
Procedures shall be developed to i=plement the require ents of the Security Plan and the Security Contingency Plan. These implementing procedures, with the exception of those non-safety related procedures i
which govern work activities exclusively applicable to or perforsed by security personnel, shall be reviewed by the Operations Committee and approved by a ne=ber of plant canagement designated by the Plant Manager.
i Security procedures not reviewed by the Operations Committee shall be reviewed and approved by the Superintendent Security.
l G.
Temporary Changes to Procedures i
Teeporary changes to Operations Committee reviewed procedures described f
in A,B,C,D,E and F above, which do not change the intent of the original procedure cay be made with the concurrence of two nenbers of the unit l
canagecent staff, at least one of whom holds a Senior Reactor Operator i
License.
Such changes shall be documented, reviewed by the Operations Com=ittee and approved by a nenber of plant management designated by the l
g Plant Manager within one month.
l Temporary changes to security procedures not reviewed by the Operations l
Com=ittee shall be reviewed by two (2) individuals knowledgeable in the i
area affected by the procedure.
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TS.6.7 5 i
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XN-NF-77-57 (A), XN hT-77-57, Supplement 1 (A), " Exxon Nuclear Power Distribution Control for Pressurised Water Reactors Phase II", May, 1981
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-nechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown nargin, and transient and accident analysis limits) of l
the safety analysis are met.
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- d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be supplied upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the j
Regional Administrator and Resident Inspector.
B. PEPORTABLE EVENTS i
i The following actions shall be taken for REPORTABLE EVENTS:
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The Co=ission shall be notified by a report submitted pursuant i
a.
to the requirements of Section 50.73 to 10 CFR Part 50, and r
b.
Each REPORTABLE EVENT shall be reviewed by the Operations Cc=ittee and the results of this review shall be submitted to the Safety Audit Con:mittee and the corporate officer.
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o C. Environ-ental Reports I
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t The reports listed belf.w shall be submitted to the Administrator of l
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the appropriate Regional NRC Office or his designate:
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1.
6nn al Radiation Environnental Monitorine Revert l
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(a) Annual Radiation Environmental Monitoring Reports covering i
the operation of the program during the previous calendar j
year shall be submitted prior to May 1 of each year.
(b) The Annual Radiation Environmental Monitoring Reports shall l
l include su=saries, interpretations, and an analysis of
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l trends of the results df the radiological environ = ental J
surveillance activities for the report period, including a l
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co=parison with preoperational studies, operational l
controls (as appropriate), and previous environmental l
surveillance reports and an assessment of the observed i= pacts of the plant operatien on the environ =ent.
The i
reports shall also include the results of land use censuses j
required by Specification 4.10.B.1.
If harnful effects or i
evidence of irreversible damage are detected by the l
conitoring, the report shall provide an analysis of the i
j proble= and a planned course of action to alleviate the
- oblem.
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(c) The Annual Radiation Environ = ental Monitoring Reports shall include sun.sarized and tabulated results in the format of i
f Regulatory cuide 4.8, Dece=ber 1975 of all radiological 8
environmental samples taken durin5 the report period. In l
the event that se=e results are not available for inclusion with the report, the report shall be submitted noting and i
explainin5 the reasons for the missing results. The i
rissing data shall be sub=itted as soon as possible in a
)
supple:entary report.
l i
(d) The reports shall also include the fo11ovin5: a su==ary
~~
description of the radiological environmental monitoring 1
program; a map of all sa=pling locations keyed to a table i
giving distances and directions from one reactor; and the results of licensees participation in the Interlaboratory j
Co:parison Program, required by Specification 4.10.C.1.
I l
2.
Environ-ental Sneefal Reports
~
1 (a) Wen radioactivity levels in samples exceed limits j
specified in Table 4.10-3, an Environmental Special Report shall be submitted within 30 days from the end of the
{
4 affected calendar quarter. For certain cases involving long analysis time, determination of quarterly averages cay extend beyond the 30 day period. In these cases the potential for exceeding the quarterly limits vill be reported within the 30 day period to be followed by the l
Environmental Special Keport as soon as practicable.
L 4
Prairie Islat Unit 1 - km3mt ib. 72, 92,105 l.
Prairie Islam thit 2 - Am3mt fb. 25, lE, 93 1
i i
= - - - ~
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UNITED STATES J-
[ t'Af,j NUCLEAR REGULATORY COMMISSION f
WASHINGTON. D.C. 2055541001
%,,..... ad i
)
NORTHERN STATES POWER COMPANY DOCKET NO. 50-306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT. UNIT NO. 2 AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No. 93 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 February 25, 1991 as revised February 22, 1993, complies with the standards and requirements of the Atomic Energy Act i
of 1954, as amended (the Act), and the Commission's rules and t
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 Commission's regulations, 1
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 Commission's regulations and all applicable requirements have been i
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-i graph 2.C.(2) of Facility Operating License No. DPR-60 is hereby amended to read as follows:
[
T i
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 93, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
)gf
/-__
William M. Dean, Acting Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: fby 4,1993 i
l k
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[
J l
r ATTACHMENT TO LICENSI AMENDMENT NO. 93 f.
FACILITY OPERATING LICENSE NO. DPR-60 l
DOCKET NO. 50-306 L
l i
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by l'
amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT TS-xiii TS-xiii l
J TS.6.1-1 TS.6.1-1 TS.6.1-2 TS.6.1-2 l
TS.6.1-3 TS.6.1-3 TS.6.1-4 f
Table TS.6.1-1 Table TS.6.1-1 Figure 15.6.1-1 Figure TS.6.1-2 TS.6.2-1 TS.6.2-1 TS.6.2-3 15.6.2-3 l
15.6.2-4 TS.6.2-4 TS.6.2-5 T5.6.2-5 r
TS.6.2-6 TS.6.2-6 l
2 15.6.4-1 T5.6.4-1 TS.6.5-4 TS.6.5-4 l
TS.6.7-5 TS.6.7-5 3
TS.6.7-6 15.6.7-6 l
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+
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TS-xiii APPENDIX A TECHNICAL SPECIF' CATIONS LTST OF FIGURES TS FIGURE TITLE 2.1-1 Safety Limits, Reactor Core Thermal and Hydraulic Two Loop Operation 3.1-1 Unit 1 and Unit 2 Reactor Coolant System Heatup Limitations 3.1-2 Unit 1 and Unit 2 Reactor Coolant System Cooldown Limitations 3.1-3 DOSE EQUIVALENT I-131 Primary Coolant Specific Activity Limit Versus Percent of RATED THERMAL PO'n'ER with the Primary Coolant Specific Activity >1.0 uCi/ gram DOSE EQUIVALENT I-131 3.9-1 Prairie Island Nuclear Generating Plant Site Boundary for Liquid Effluents
?.9-2 Prairie Island Nuclear Generating Plant Site Boundary for Gaseous Effluents I
3.10-1 Required Shutdown Margin Vs Reactor Boron Concentration 4.4-1 Shield Building Design In-Leakage Rate 2
Prairie Island Unit 1 - Avdmt ib. 91, 92, 105 Prairie Island thit 2 - kmtent fb. 24,85,93 m
o TS.6.101 6.0 ADMINISTPATIVE CONTROLS 6.1 Organization A.
The Plant Manager 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. The Plant Manager shall delegate in writing the succession to this responsibility during his absence. The Plant Manager has the responsibility for the Fire Protection Program E.
Onsite and Offsite Organizations Onsite and offsite organizations shall be established for plant operation and corporate management. The onsite and offsite organizations shall include the positions responsible for activities affecting plant safety.
- 1. 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 Operational Quality Assurance Plan or the Updated Safety Analysis Report.
- 2. There shall be an individual executive position (Vice President Nuclear Generation) in the offsite organization having 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.
- 3. There shall be an individual management position (Plant Manager) in the onsite organization having responsibility for overall unit safe operation and who shall have control over those onsite resources necessary for safe operation and maintenance of the plant.
- 4. 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.
C.
Plant Staff:
- 1. Each on daty shift shall be composed of at least the minimum shift crew composition shown on Table TS.6.1-1.
- 2. For each reactor that contains fuel:
a licensed operator in the control room.
l Prairie Islard thit 1 - A~entent !b. 25, ts, U,16 Prairie Island thit 2 - Mentent fu. 22,43,55,98
~
TS.6.1-2 3.
At least two licensed operators shall be present in the control room during a reactor startup..a scheduled reactor shutdown, and during recovery from a reactor trip. These operators are in addition to those required for the other reactor.
4 An individual qualified in radiation protection procedures shall be on site when fuel is in a reactor.
5.
All refueling operations shall be directly supervised by a licensed Senior Reactor Operator or a Senior Reactor Operator Limited to Fuel Handling who has no other concurrent respons.
ibilities during this operation.
6.
A fire brigade of at least five members shall he maintained on site at all times.* The fire brigade shall not include the six members of the minimum shift crew for safe shutdown of the reactors.
7.
The General Superintendent Plant Operations shall be formerly licensed or hold a current license on a similar tyTe plant.
8.
At least one member of plant management holding a current Senior Reactor Operator license shall be assigned to the plant operations group on a long term basis (approximately two years). This individual shall not be assigned to a rotating shift.
D.
Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1 1971 for comparable positions, except for (1) the General Superintendent Radiation Protection who shall meet or l
exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Manager who shall have a bachelors degree or equivalent in a.
l
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scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents, and (3) the General Superintendent Plant Operations who shall meet the requirements of ANSI N18.1-1971, except that NRC license requirements are as specified in Specification 6.1.C.7.
The training l
program shall be under the direction of a designated member of Northern.
States Power management.
- 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 of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.
Prajrje Island thjt 1 ATnfTnt fb. 2b,, 46, y, E 105 Prairie Isinad imt 2 - Amnant !b. 27 4, w,,/s, 93 l
____----______________--__--_______j
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.a e
1 1.
TS.6.1-3 t
5 E.
A training program for the fire brigade shall be maintained under the direction of a designated member of Northern States Power management.
This program shall meet the requirements of Section 27 of the NFPA Code -
1976 with the exception of training scheduling.
Fire brigade training shall be scheduled as set forth in the training program.
l J
F.
Administrative procedures shall be developed and implemented to limit the
{
vorkins hours of unit staff who perform safety-related functions; e.g.,
senior reactor operators, reactor operators, health physicists, auxiliary i
operators, and key maintenance personnel.
Procedures shall include the following provisions:
l 1.
Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel l
work a nominal 40-hour week while the plant is operating. However, in the event that unforeseen problems require substantial amounts of a
overtime to be used, or during extended periods of shutdown for l
refueling, major maintenance or major plant modifications, on a temporary basis, the following guidelines shall be followed:
i 1
1 a.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> t
straight excluding shift turnover time.
- b. Overtime should be limited for all nuclear plant staff personnel so j
that total work time does not exceed 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> in i
j any seven day period, all excluding shift turnover time.
Individuals should not be required to work more than 15 consecutive days without two consecutive days off.
c.
A break of at least eight hours including shift turnover time should i
be allowed between work periods.
(
d.
Except during extended shutdown periods, the use of overtime should
[
be considered on an individual basis and not for the entire staff on e
a shift.
~
e.
Shift Emergency Coordinator (SEC) on-site rest time periods shall l
l not be considered as hours worked when determining the total work time for which the above limitations apply.
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Prairie Island Unit 1 - Nealmt.1b. f3',105 4
Prairie Island trit 2 - Aramt th. 2, 93 1
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TS.6.1-4 l
2.
Any deviation from the above guidelines shall be authorized by the Plant Manager or designee, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
During plant emergencies, the Emergency Director shall have this authority. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not allowed.
I e
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l Prairie Island thit 1 - ATntent !b.105 Prairie Island thit 2 - Icentent lb. 93
TABLE TS.6.1-1 bq%
MINIMUM SilIFT CREV COMPOSITION (Note 1 and 3) 5 5' W t;-
w A
CATEGORY BOTil UNITS IN COLD SilUTDOWN ONE UNIT IN COLD SIIUTDOW BOTil UNITS ABOVE COLD
((
OR REFUELING SIIUTDOWN OR REFUELING SIIUTDOW AND SIIUTDOWN r+ r+
ONE UNIT ABOVE COLD SIIUTDOWN Na e i k No. Licensed Senior 2 (Note 2) 2 (Notes 2, 4) 2 (Note 4)
{ g Operators (LS0)
- 9+
Total No. Licensed 4
4 5
gg Operators (LSO & LO)
( Total No. Licensed &
6 7
8 P2 Unlicensed Operators Bl d Shift Manager (Note 5) 0 1
1 l
8 NOTES:
1.
Shift crew composition may be one less than the minimum requirements for a period of time not to exceed two hours in order to accommodate an unexpected absence of one duty shift crew member provided immediate action is taken-to restore the shift crew composition to within the minimum requirements specified.
2.
Does not include the licensed Senior Reactor Operator, or Senior Reactor Operator Limited to Fuel llandling, supervising refueling operations.
3.
Each LSO and ID shall be licensed on each unit.
4 One LSO shall be in the control room at all times when a reactor is above cold shutdown.
g a 5.
The Shift Manager performs the functions of the Shift Technical Advisor l
7,.
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TS.6.2-1 3
6.2 Review and Audit Organizational units for the review and audit of facility operations shall be constituted and have the responsibilities and authorities t
outlined below:
A.
Egfety Audit Comittee (SAC)
The Safety Audit Committee provides the independent review of plant operations from a nuclear safety standpoint. Audits of plant operation are conducted under the cognizance of the SAC.
1.
Membership The SAC shall consist of at least five (5) persons.
a.
b.
The SAC chairman shall be an NSP representative, not having line responsibility for plant operation, appointed by the corporate officer. Other SAC members shall be appointed by the corporate officer or by such other person as he may designate. The Chairman shall appoint a Vice Chairman from the SAC membership to act in his absence.
No more than two members of the SAC shall be from groups c.
holding line responsibility for operation of the plant, i
d.
A SAC member may appoint an alternate to serve in his absence, with concurrence of the Chairman. No more than one alternate shall serve on the SAC at any one time. The alternate member shall have voting rights.
2.
Qualifications The SAC members should collectively have the capability a.
required to review activities in the following areas:
nuclear power plant operations, nuclear engineering, chemistry and radiochemistry, metallurgy, instrumentation and control, radiolcgical safety, mechanical and electrical engineering, quality assurance practices, and other appro-priate fields associated with the unique characteristics of the nuclear power plant.
Prairie Island Unit 1 - Amrent fb. 73, #3, ff, 73,105 Prairie Island Unit 2 - kentent fb. 7, #3, 55, fd, 93 f
i f
_m
_.-m.
2-L a
. = _
e TS.6.2-3 i
i f.
Investigation of all Reportable Events and events requiring Special Reports to the Commission.
g.
Revisions to the racility Emergency Plan, Facility Security Plan, and the Fire Protection Program.
l h.
Operations Committee minutes to determine if matters considered by that Comrittee involve unreviewed or unresolved safety questions.
l 1.
Other nuclear safety matters referred to the SAC by the Operations Committee, plant management or company management.
J.
All recognized indications of an unanticipated deficiency in some aspect i
of design or operation of safety related structures systems, or components.
i k.
Reports of special inspections and audits conducted in accordance with Specification 6.3.
l 1.
Changes to the Offsite Dose Calculation Manual (ODCM).
m.
Review of investigative reports of unplanned releases of radioactive material to the environs.
6.
Audit - The operation of the nuclear power plant shall be audited formally under the cognizance of the SAC to assure safe facility operation.
a.
Audits of selected aspects of plant operation, as delineated in Paragraph 4.4 of ANSI N18.7-1972, shall be performed with a frequency commensurate 1
with their nuclear safety significance and in a manner to assure that an audit of all nuclear safety related activities is completed within a period of two years.
The audits shall be performed in accordance with appropriate written instructions and procedures.
l b.
Audits of aspects of plant radioactive effluent treatment and radio-icgical environmental monitoring shall be performed as follows-i l
- 1. Inplementation of the Offsite Dose Calculation Manual at least once every rwo years.
- 2. Implementation of the Process Control Program for solidification of radioactive wastes at least once every two years.
- 3. The Radiological Environmental Monitoring Program and the results thereof, including quality controls, at least once every year.
c.
Periodic review of the audit program should be performed by the SAC at least twice a year to assure its adequacy.
d.
Written reports of the audits shall be reviewed by the Vice President Nuclear Generation, by the SAC at a scheduled meeting, and by members
)
of management having responsibility in the areas audited.
2 Prairie Isla*d thit 1 - kentent fb. 97, /A U, Tf,105 Prairie Island Unit 2 - kerdrnt fb. G, 53, fE f6, 93
~.
TS.6.2-4 l
i 7.
Authority l
The SAC shall be advisory to the Vice President Nuclear Generation.
i
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8.
Records Minutes shall be prepared and retained for all scheduled meetings of d
the Safety Audit Committee. The minutes shall be distributed within one month of the meeting to the Vice President Nuclear Generation, each l
[
member of the SAC and others designated by the Chairman. There shall be a formal approval of the minutes.
t i
9.
Procedures
{
A written charter for the SAC shall be prepared that contains:
l i
a.
Subjects within the purview of the group.
b.
Responsibility and authority of the group.
I c.
Mechanisms for convening meetings.
q d.
Provisions for use of specialists or subgroups.
1 Authority to obtain access to the nuclear power plant operating I
e.
record files and operating personnel when assigned audit functions.
i f.
Requirements for distribution of reports and minutes prepared by the group to others in the NSP organization.
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s Prairie Island thit 1 - kmamt Ib.12, 57, Ef,105 Prairie Island thit 2 - kentent tb. 7,53,55,98 i
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TS.6.2-5 i
i B.
Operations Committee (OC) 1.
Membership The Operations Committee shall consist of at least six (6) regular t
members drawn from the key supervisors of the onsite staff. The key r
supervisors include, at least, the following positions: Plant Manager, General Superintendent Plant Operations, General Superintendent Plant Maintenance, General Superintendent Radiation Protection and Chemistry and Plant Engineering Supervisors.
Alternates to the regular members shall be designated in writing by the Chairman to serve on a temporary basis. No more than two alternates shall participate as voting members of the Operations Committee at any one time.
The Plant Manager shall serve as Chairman of the Oc and shall j
4 appoint a regular member to act as Chairman in his absence.
2.
Meeting Frequency "ihe Operations Committee will meet on call by the Chairman or as requested by individual members and at least monthly.
3.
Quorum A majority of the membership, including the Chairman.
3 4
Responsibilities - The following subjects shall be reviewed by the Operations Committee:
4 a.
Proposed tests and experiments and their results.
- b. Modifications to plant systems or equipment as described in the Updated Safety Analysis Report and having nuclear safety significance or which involve an unreviewed safety l
question as defined in Paragraph 50.59 (c), Part 50, Title l
10, Code of Federal Regulations.
l 7
I
- c. Proposals which would effect permanent changes to normal and emergency operating procedures and any other proposed changes or procedures that will affect nuclear safety as determined by the Plant Manager.
?
- d. Proposed changes to the Technical Specifications or operating i
licenses.
All reported or suspected violations of Technical Specifica-e.
tions, operating license requirements, administrative procedures, operating procedures. Results of investigations, including evaluation and recommendations to prevent recurrence vill be reported in writing to the Vice President Nuclear Generation and to the Chairman of the Safety Audit Committee.
Prairie Islard init 1 - krnrent fb. 43, if, 73,105 3
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Prairie Islard Unit 2 - Amtent !b.13, f3, Ed, 93 d
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TS.6.2-6 f.
Investigations of all Reportable Events and events requiring Special Reports to the Commission.
g.
Drills on energency 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 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.
1 i.
Special reviews and investigations, as requested by the Safety Audit i
Committee.
- j. Review of investigative reports of unplanned releases of radioactive material to the environs.
)
k.
All che.nges to the Process Control Program (PCP) and the Offsite Dose Cniculation Manual (ODCM).
1.
The review of safety evaluations, when safety evaluations are q
required by 10 CFR Part 50, Section 50.59, for procedures or i
procedure changes to verify that such actions do not constitute an I
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 will be followed. A written summary of the disagreement will be sent to the Vice President Nuclear Generation and the Chairman l
of the SAC for review.
6.
Records 4
l Minutes shall be recorded for all meetings of the OC and shall 4
identify all documentary material reviewed.
The minutes shall be distributed to each neaber of the OC, the Chairuan and each nember of the Safety Audit Committee, the Vice President Nuclear Generation and others designated by the OC Chairman.
7.
Procedures A written charter for the OC shall be prepared that contains:
Responsibility and authority of the group a.
Preirie Islard thit 1 - Amtmt fb. f?, E?, 73, PJ, N,105 Prairie Islard thit 2 - kmtmt fb.13, E3, f6, 73, 83, 93 I
i
l TS.6.4-1 l
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i 6.4 SAFETY LIMIT VIO1.ATION 1
1 11.. Safety Limit is exceeded, the reactor shall be shut down and the I
j Commission shall be notified immediately.
It shall also be promptly reported to the Vice President Nuclear Generation and the Chairman of the <
l j
l Safety Audit Committee, or their designated alternates. A safety limit
]
l violation report shall be prepared. This report shall describe
{
i (1) applicable circumstances precedin5 the violation, (2) effects of the-I j
violation upon facility components, systems or structures, and (3) the f
basis for corrective action taken to preclude recurrence. The report j
shall be reviewed by the Operations Committee. The safety limit l
I violation report shall be submitted to the Commission, the Vice President Nuclear Generation and the Safety Audit Committee within two weeks of the 2
event.
l Operation shall not be resumed until authorized by the Nuclear Regulatory l
Commission.
l
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i Prairie Island Unit 1 - kmtmt Ib. 7, 47, 105 Prairie Island Unit 2 - kmtmt !b. 4, #3, 93 l
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TS.6.5-4 E.
Offsite Dose Calculation Manual (ODCM)
The ODCM shall be approved by the Commission prior to initial implementation.
Changes to the ODCM shall satisfy the following require =ents:
1.
Shall be submitted to the Commission with the Semi-Annual Radioactive Effluent Report for the period in which the change (s) were made effective.
This sub=ittal shall contain:
a.
sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.
Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with a revision date, together with appropriate analyses or evaluations justifying the change (s).
- b. a determination that the change vill not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
docu=entation of the fact that the change has been reviewed and found acceptable by the Operations Committee.
2.
Shall become effective upon review and acceptance by the Operations Committee.
F.
Security Procedures shall be developed to implement the requirements of the Security Plan and the Security Contingency Plan. These implementing procedures, with the exception of those non-safety related procedures which govern work activities exclusively applicable to or performed by security personnel, shall be reviewed by the Operations Committee and approved by a member of plant management designated by the Plant Manager.
Security procedures not reviewed by the Operations Committee shall be reviewed and approved by the Superintendent Security.
l G.
Temporary Changes to Procedures Temporary changes to Operations Committee reviewed procedures described in A,B,C,D,E and F above, which do not change the intent of the original procedure may be made with the concurrence of two members of the unit management staff, at least one of whom holds a Senior Reactor Operator License.
Such changes shall be documented, reviewed by the Operations Committee and approved by a member of plant management designated by the Plant Manager within one month.
4 Temporary changes to security procedures not reviewed by (he Operations Committee shall be reviewed by two (2) individuals knowledgeable in the area affected by the procedure.
Prairie Island thit 1 - kEnfE1 ID. M, N, [b E
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Prairie Island thit 2 - kmfmt fb. f2, 73, 75, 93 G
.o TS.6.7-5 O
XN-NF-77-57 (A). IN-NF-77-57, Supplement 1 (A),
Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II", May, 1981
- c. The core operating limits shall be determined such that a'21 applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
- d. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be supplied upon issuance, for each reload cycle, to the NRC Docu=ent Control Desk with copies to the Regional Administrator and Resident Inspector.
B. EEPORTAME EVB'TS The following actions shall be taken for REPORTABLE EVENTS:
The Commission shall be notified by a report submitted pursuant a.
to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Operations Cocaittee and the results of this review shall be submitted to the Safety Audit Committee and the corporate officer.
Prairie Island trat 1 - Nendmt ft. E4, E?, 73, 91, 92, 73,105 Prairie Island Lnit 2 - kentent !b. E, f2, f6, 2J, P3, P6, 93
$ W@
9&e G W -hWem&hpp See pMWEh
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6 TS.6.7-6 o
C, Environrental Reports The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:
1.
Annual Radiation Environmental Monitorint Report (a) Annual Radiation Environmental Monitoring Reports covering the operation of the program during the previous calendar year shall be submitted prior to May 1 of each year.
(b) The Annual Radiation Environmental Monitoring Reports shall include summaries, interpretations, and an analysis of trends of the results df the radiological environmental surveillance activities for the report period, including a l
comparison with preoperational studies, operational 6
controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environ =ent.
The reports shall also include the results of land use censuses required by Specification 4.10.B.1.
If harmful effects or evidence of irreversible da= age are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.
(c) The Annual Radiation Environmental Monitoring Reports shall include summarized and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environ = ental sa=ples taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The cissing data shall be submitted as soon as possible in a supple =entary report.
(d) The reports shall also include the following: a su= mary description of the radiological environmental monitoring
~~
program; a map of all sa=pling locations keyed to a table giving distances and directions from one reactor; and the results of licensees participation in the Interlaboratory i
Comparison Program, required by Specification 4.10.C.1.
2.
Environnental Special Reports I
(a) When radioactivity levels in sa=ples exceed limits
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i specified in Table 4.10-3, an Environmental Special Report shall be submitted within 30 days from the end of the affected calendar quarter. For certain cases involving long analysis ti=e, determination of quarterly averages cay extend beyond the 30 day period. In these cases the potential for exceeding the quarterly limits will be reported within the 30 day period to be followed by the Environnental Special Report as soon as practicable.
P airie Islan1 triit 1 - keatmt ib. N, B,105 Prairie island thit 2. kerdmt fb. E, N, 93
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