ML20031G528
| ML20031G528 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/08/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031G529 | List: |
| References | |
| NUDOCS 8110230173 | |
| Download: ML20031G528 (9) | |
Text
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o, UNITED STATES E
( ',g NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 g
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CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 67 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated DecemLer 18, 1980, as supplemented May 7,1981, 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 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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e 9110230173 811000 PDR ADOCK 05000255 p
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B (Environmental Protection Plan), as revised through Amendment No. 67, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is ef fective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t/
vmM Y:-
Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 8, 1981 l
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I ATTACHMENT TO LICENSE AMENDMENT NO. 67 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revised Appendix A Technical Specifications by removing the.following pages and by inserting the enclosed pages. The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
REMOVE INSERT iii iii 3-1b 3-81a 4-11a 6-la 6-la 6-4 6-4 6-33 6-33 I
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TABLE OF CONTENTS (Contd) i i
Section Description Page 4.0 SURVEILLANCE REQUIREMENTS (Contd) 4.12 Augmented Inservice Inspection Program for High Energy Lines Outside of Containment 4-60 4.13 Reactor Internals Vibration Monitoring 4-65 4.14 Augmented Inservice Inspection Program for Steam Generators 4-68 4.15 Primary System Flow Measurement 4-70 4.16 Inservice Inspection Program for Shock Suppressors (Snubbers) 4-71 4.17 Fire Protection System 4-75 5. 0 --
DESIGN FEATURES 5-1 5.1 Site 5-1 5.2 Containment Design Features 5-1 5.3 Nuclear Steam Supply System (NSSS) 5-2 5.4 Fuel Storage 5-3 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 Responsibility 6-1 6.2 Organizatioh 6-1 6.3 Plant Staff Qualifications 6-1 6.4 Training 6-1 6.5 Review and Audit 6-5 6.6 (Deleted) 6-9 i
6.7 Safety Limit. Violation 6-9
- 6. 8,,
Procedures 6-10 6.9 Reporting Requirements 6-11 6.10 Record Retention 6-26 6.11 Radiation Protection Program 6-27 6.12 High Radiation Area 6-28 6.13 Fire Protection Inspection 6-33 6.14 Environmental Qualifi. cation 6-33 6.15 Systems Integrity 6-33 6.16 Iodine Monitoring 6-33 S
SPECIAL TECHNICAL SPECIFICATIONS PURSUANT TO AGREEMENT S-1 S-1 (Deleted)
S-2 S-2 Liquid Radwaste System Modif' cation S-5 S-3 through S-5 (Deleted) i iii Amendment No. J/, AB, 66, 67
t 3.1 PRIMARY COOLANT SYSTEM (Cont'd) l 3.1.1 Operable Components (Cont'd)
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1.
The PCS shall not be heated or maintained above 325 F unless a l
minimum of 375-kW of pressurizer heater capacity is available from both buses 1D and lE. JShould heater capacity from either bus 1D or lE fall below 375 kW, either restore the inoperable I
heaters to provide at least 375 kW of heater capacity from both buses 1D and lE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in hot' shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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i 3-lb tnendment No. 67
Table 3.17.4 (Cont'd)
Minimum Minimum Permissible Operabl e Degree of Bypass No.
Functional Unit Channels Redundancy Conditions 8.
Pressurizer Water 2
1 Not Required in Level (LI-0102)
Cold or Refueling Shutdown 9.
Pressurizer Code Safety 1 per None Not Required below Relief Valves Position valve 325'F Indication (Acoustic Monitor or Temperature Indication) 10.
Power Operated Relief 1 per None Not required when Valves (Acoustic valve PORV isolation valve Monitor or Temperature is closed and its Indication) indication system is operable 11.
PORY Isolation Valves 1 per None Not required when Position Indication valve reactor is depressurized and vented through a vent gy 1.3 sq. in.
12.
Subcooling Margin 1
None Not Required Monitor Below 515 F i
13.
Auxiliary Feed Flow 1 per None Not Required l
Rate Indication Steam Below 325 F Generator j
l 14.
Auxiliary Feed Pump 1 per (e)
None Not Required i'
Auto Initiation Pump Below 325 F Circuitry
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(e) With one auxiliary feed pump automatic initiation circuit inoperable, in lieu of the requirement of 3.17.2, provide a second licensed operator in the control room within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. With both inoperable, in lieu of following the requirements of 3.17.2, start and maintain in operation the turbine driven auxiliary feed pump.
3-81a Amendment No. 67
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Table 4.1.3 (Cont'd)
Surveillance Channel Description Function Frequent _y, Surveillance Method i
15 Auxiliary Feed Pump a.
Check M (5) a.
Comparison of Channels Flow Indication b.
Calibrate R
b.
Known Differential Pressure Applied to sensors 16.
Auxiliary Feed Pump a.
Test M (3) (S) a.
Internal Test Signal Auto Initiation b.
Calibrate R
b.
Known Differential Pressure Applied to Sensors 17.
Power Operated Relief Valves and Pressurizer Code Safety Relief Valves Position Indication a.
Temperature a.
Calibrate R
a.
Known Resistance Substitute for RTD b.
Check S
b.
Comparison of Channels b.
Acoustic Monitor a.
Calibrate R
a.
Inject Calbrated Test Signal 18.
Subcooling Margin a.
Check S
a.
Comparison of Channels Monitor b.
Calibrate R
b.
Known Resistance Substituted for RTD Coincident With Known Pressure Input (4)
(3) Test method to be alternated to include starting auxil'ary feedwater pump from the control room hand switch, from the breaker and from the. automatic start in a three-month period.
(4)In conjunction with Item 4(b), Table 4.1.1.
(5)It is not necessary to perform the specified testing during the cold shutdown condition.
4-Il a Amendment No. 67 I
r 6.3.3 The. Shift Technical Advisor (STA) shall have a bechelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Nuclear Training Administrator and shall meet or exceed the requirements and recom-mendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR, Part 55, 6.4.2 A training program for the fire brigade shall be maintained under the direction of the Plant Training Coordinator and shall, as practical, meet or exceed the requirements of Section 27 of the NFPA Code.
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6-la Amendment No. 3f, )(, 67
TABLE 6.2-1 Minimum Shift Crew Composition Minimum shift crew shall be as follows except when the plant conditions specified in Paragraph (a) and (b) below have been established:
Shift Supervisor - 50L Control Operators (2) - OL Auxiliary Operators"(2)
(a)
Cold Shutdown Condition or Refueling Shutdown Condition Shift Supervisor - S0L Control Operator - OL i
Auxiliary Operators'(2)
(b)
Refueling Operators
- Shift Supervisor - S0L j.
Control Operator - OL Auxiliary Operators (2)
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- Does not include additional personnel required when core alterations are being conducted.
See Paragraph 6.2.2.e.
SOL - Senior Reactor Operator i:
OL - Reactor Operator 6-4 AmendmentNo.)(,67
6.13 FIRE PROTECTION INSPECTION 6.13.1 An independent fire protection and loss prevention inspection shall be performed annually utilizing either qualified off-site licensee personnel or an outside protection firm.
6.13.2 An inspection by an outside qualified fire consultant shall be per-formed at intervals no greater than 3 years.
6.14 ENVIRONMENTAL QUALIFICATION 1.
By no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of:
Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Cuidelines); or, NUREG-0588 " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment", December 1979.
Copies of these documents are attached to Order for Modification of License DPR-20 dated October 24, 1980.
2.
By no later than December 1,1980, compkte and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the D0R Guidelines or NUREG-0588.
Thereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
6.15 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the follo' wing:
1.
Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at a frequency not l
to exceed refueling cycle intervals.
6.16 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately detennine the airborne iodine concentration in vital areas unde accident conditions. This program shall include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and l
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Provisions for maintenance of sampling and analysis equipment.
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'6-33 Amendment No. )f,67
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