ML20073R485
| ML20073R485 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/31/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073R487 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 9106100085 | |
| Download: ML20073R485 (9) | |
Text
..
- g. arc p
e' <,
i UNITED STATES
?.! J;),
i NUCLEAR REGULATORY COMMISSION p.
Nb f
WASHINGTON. D C. 20%5
%....[+/
CONSUMERS POWER COMPAtlY a
PALISADES PLAf4T DOCKET NO. 50-255 AMENDMENT TO FAC18.!TY OPERATING LICENSE Amendment No.
139 License No. OPR-20 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated September 21, 1988, as supplemented July 18, and Septerr.ber 28, 1990, complies with the standards and requirements of the Atomic Energy Act of D54, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter 1; 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 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.
l l
9106100085 910531 DR ADDCK 0500 5
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licensi:
amendment and Paragraph 2.C.2 of facility Operating License No. DPR-20 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
139, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented not later than January 31, 1991.
FOR THE NUCLEAR REGULATORY COMMISSION GA 2
L. B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects lil/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 31, 1991 l
l l
l 1
- -.. ~. - -.. _. _.... - - - _ -,. -.
ATTACHttENT 10 LICENSF AMENDMENT NO. 139 FACILITY OPERATING LICENSE NO. DPR-20 l
DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT vi vi 6-1 6-1 6-la 6-lb 6-2 6-2 6-2a 6-3 6-3 6-3a 6-5 6-5
=~y v.
-,rw--
er,y,.---e.--.
-..w..--,
- v. m w,.,me-,-
.w,
.---e.,--,
_,-,,-,.%,-.--.-.,.-,,-.n- - - -
m
.w
-- - =, --
-,w, mww-w<v.-..
+--m---
PAllSADES PLANT TECHN1 CAL SPECIFICATIONS TABLE OF CONTENTS APPENDIX A EL(TJfB DESCRIP110N EAG[ ND 4.0 SURVEllLANCE REQUIREMENTS (Continued) 4.24.6 Gaseous Waste System 4 01 4.24.7 Solid Radioactive Waste 4 91 4.24.8 Total Dose 4 91 Table 4.24 1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 4 92 Table 4.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 4-93 Table 4.24 3 Radioactive Liquid Waste Sampling and Analysis Program 4 95 Table 4.24 5 Radioactive G.seous Waste Sampling and Analysis Program 4-97 5.0 DESIGN FEATURES 51 5.1 SITE 51 5.2 CONTAINMENT DESIGN FEATURES 5-1 5.2.1 Containment Structu.es 51 5.2.2 Penetrations 52 5.2.3 Containinent Structure Cooling Systems 52 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5-2 5.3.1 Primary Coolant System 52 5.3.2 Reactor Core and Control 53 5.3.3 Emergency Core Cooling System 53 5.4 FUEL STORAGE 54 5.4.1 New Fuel Storage 54 5.4.2 Spent Fuel Storage 5 4a Figure 5 1 Site Environment TLD Stations 5-5 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 RESPONS!BIL11Y 61 6.2 ORGANIZATION 61 6.2,1 Offsite and Onsite Organizations 6-1 1
6.2.2 Plant Staff 62 6.3 PLANT STAFF QUAllflCATIONS 6-3 Table 6.2-1 Minimum Shift Crew Composition 6-4 6.4 TRAINING 65 vi Amendment No EE,JEE,J0E 127,139 l
AMINI $TRt.TIVf CONTR0l $
6.1 RESPONSIBillTY 6.1.)
The Plant General Manager shall be responsible for overall plant operation and shall delegate in writing the succession for this responsibility during his absence.
6.1.2 The Shift Supervisor or in his absence from the control room, the second licensed senior operator on duty sha's be responsible for the shift comand function. A directive to this effect shall be issued annually by the Vice President - Nuclear Operations.
6.2 ORGANIZATION 6.2.1 OffSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be establishea for plant operation and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the Palisades Plant.
a.
Lines of authority, responsibility and comunication 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 positions, or in equivalent forms of documentation.
These requirements shall be documented in the FSAR.
b.
The Plant General Manager shall be responsible for overall plant safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the
- plant, c.
The Vice President - Nuclear Operations shall have crrporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technica', support to the plant to ensure nuclear safety, d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they sla',1 have sufficient organizational freedom to ensure their independence from operating pressures.
6-1 Amendment No. 72,77,EE,7E,JPE,139
ADMINISTRAT]VF CONTR0l5 6.2.2 flANT STAFF I
a.
Each on duty shif t shall be composed of at least the minimum shift crew composition shown in Table 6.2 1.
b.
At least one licensed Senior Reactor Operator shall be in the l
control room at all times during conditions other than cold shutdown or refueling. In addition to this Senior Reactor Operator, at least one licensed Reactor Operator or Senior Reactor Operator shall be present at the controls at all times when fuel is in the reactor, c.
ARadiationJafetyTechnicianshallbeonsitewhenfuelisin the reactor.
d.
All core alterations, after the initial fuel loading, shall either be performed under the direct supervision of a licensed Senior Reactor Operator or Senior Operator holding a license j
limited to fuel handling.
During this time, no other responsibilities shall be assigned to this individual.
e.
A Fire Brigade of at least 5 mtmbers shall be maintained on site at all times.* The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown or any personnel required for other essential functions during a fire emergency, f.
Administrative procedures shall limit the working hours of Plant staff who perform safety related functions.
In the event that overtime i; :::d. '6ne following guidelines shall be followed:
A.
An individual shall 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 time).
B.
An individual shall 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 /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor n. ore than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i any seven day period (all excluding shift turnover time).
C.
A break of at least eight hours shall be allowed between work periods (including shift turnover time).
- The Radiation Safety Technician and the Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accomodate unexpected absence provided imediate action is taken to restore the minimum requirements.
6-2 Amendment No. U U,UE,139
l ADM}NISTRATIVE CONTROL 5 6.2.2.f PLANT STAFF (Continued)
D.
Except during extended shutdown periods the use of overtime should be considered on an individual basir and not for the entire staff on a shift.
Deviations from the overtime guidelines shall be authorized by the Plant General Manager or his Alternate.
The basis for granting the deviation shall be documented.
Routine deviations are not to be authorized.
Individual overtime will be reviewed monthly by the Plant General Manager or his designee to assure that excessive hours have not been assigned.
6.2.3 (DELETED) 6-2a Amendment No.139
l ADMIN}STRATIVfCONTR$S 6.3 plant STAFF OVAllFICAT10NS 6.3.1 Each member of the plant Staff shall meet or exceed the minimum qualifications of ANSI N18.]-1971 for comparable positions.
6.3.2 A Radiation Safety Manager shall be designated by the Plant General Manager and shall meet or exceed the qualifications of a Radiation Protection Manager as defined in Regulatory Guide 1.8, September 1975.
The Radiation Safety '4anager shall have direct access to Plant General Manager in the matters of radiation safety.
6.3.3 The Shift Technical Advisor shall have a bachelor's degree or equivalent and the Shift Engineer shall have a bachelor's degree in a scientific or engineering discipline.
Specific training for both the Shift Technical Advisor and the Shif t Engineer shall include plant design, operations, and response and analysis of the ;,lant for transients and accidents.
The Shift Engineer shall hold a Senior Reactor Operator License.
l 6.3.4 The Plant Safety and Licensing Staff who perform the reviews specified in 6.5.3 shall meet or exceed thc minimum qualifications of ANS 3.1-1987, Section 4.7.1 and 4.7.2.
A Senior Reactor Operator License or certification shall be considered equivalent to a bachelors degree for the purpose of this specification for r.o more than two individuals.
6.3.5 Either the Plant Operations Manager or the Plant Operations Superintendent will hold an SRO license and meet the other requirements of Section 6.3.1 of these Technical Specifications (as applicable to the Operations Manager in ANSI N18.1).
The individual holding the SR0 license shall be responsible for directing the activities of the licensed operators.
- For the purpose of this section, " Equivalent,' as utilized in Regulatory Guide 1.8 for the bachelor's degree requirement, may be met with four years of any one or combination of the following:
(a) Formal schooling in science or engineering, or (b) operational or technical experience / training in nuclear power.
6-3 Amendment No 37,4,70E.139
ADMIN]STRATIVf CONTR0l5 6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant staff andAppendix*A"ofl shall be maintained and shall meet or exceed the requirements and recomendations of Section 5.5 of ANSI N18.1-1971 10 CFR Par t 55.
6.4.2 The Fire Brigade training program shall be maintained and shall, as l
practicable, meet or exceed the requirements of Section 27 of the NFPA Code 1975.
Fire brigade training drills shall be held at least quarterly.
6.5 REVIEW AND AUDIT 6.5.1
}UJii REVIEW COMMITTEE (PRC) 6.5.1.1 FUNCTION The Plant Review Comittee (PRC) shall function to advise the Plant General Manager on all matters related to nuclear safety.
6.5.1.2 {p!iP051T10N The PRC shall be composed :,f:
Plant General Mana Chairman:
Operations Manage ger Member:
viember:
Engineering and Maintenance Manager, Member:
Radiological Services Manager Member:
Plant Safety and Licensing Director, Member:
Reactor Engineering Superintendent Member:
Operations Superintendent Member:
Instrumentation and Control Superintendent Member:
Shift Supervisor or Shift Engineer (s) (1)
- may serve as Designated Alternate for the Chairman 6.5.1.3 ALTERNATES Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve nn a temporary basis. No more than two alternates shall participate as voting members at any one time in PRC activities.
Members identified with a asterisk'*) above may function as the Designated Alternate for the Chairman, and in so doing, are not consid ued alternate members for voting purposes.
65 Amendment No. JE,/E,7),JEE,J77, 139
_ -