ML18052A719

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Proposed Tech Specs Replacing 850111 & 0306 Changes
ML18052A719
Person / Time
Site: Palisades Entergy icon.png
Issue date: 09/29/1986
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18052A717 List:
References
NUDOCS 8610090056
Download: ML18052A719 (27)
v • d • e


Text

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED PROVISIONAL OPERATION LICENSE AND TECHNICAL SPECIFICATION PAGE CHANGES September 29, 1986

\{ 8610090056 860929 :* I I ADOCK

\ . . -25 Pages TSOP0686-0104-NL04 i' -3 F. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Physical Security, Safeguards Contingency, and Guard Training and Qualification Plans, including amendments made pursuant to the provisions of 10 CFR 50 .. S4(p). The approved plans, which contain Safeguards Information described in 10 CFR 73.21, are collectively entitled, "Palisades Nuclear Power Plant Security Plan", dated February 20, 1979 with Revision 1 dated March 27, 1979 (transmitted

  • March 30, 1979), 'Revision 2 dated June 13, 1980 (transmitted June 8, 1980), Revision 3 dated November 10, 1980 (transmitted December 10, 1980), Revision 4 dated March 18, 1981 (transmitted March 27, 1981), Revision 5 dated October 1, 1981 (transmitted November 6, 1981), Revision 6 dated October 1, 1982 (transmitted November 5, 1982); "Palisades Nuclear Plant Safeguards Contingency Plan", dated July 11, 1980 (transmitted July 24, 1980); and "Palisades Nuclear Plant Suitability, Training and Qualification Plan", dated June 26, 1980 (transmitted July 17, 1980), Revision 1 dated October 1, 1982 (transmitted November 5, 1982) and supplemental Revision 1 page changes dated October 1, 1982 (transmitted June 20, 1983). (By Amendment No. 78 dated 11/7/83 Paragraphs 3.G and 3.I have been combined with the existing paragraph 3.F and paragraph 3.H has been deleted).

Proposed TSP0686-0104C-NL04

)* ADMINISTRATIVE CONTROLS 6.1 6 .1.1 6.1. 2 6.2 OFFSITE 6.2.1 PLANT STAFF 6.2.2 RESPONSIBILITY The Plant General Manager shall be responsible for overall plant operation and shall delegate in writing the succession for.this responsibility during his absence. The Shift Supervisor or in his absence from the control room, the second licensed senior operator on duty shall be responsible for the shift command function.

A directive to this effect shall be issued annually by the Vice President

-Nuclear Operations.

ORGANIZATION The offsite organization for plant management and technical support shall be as shown in Figure 6.2-1. The .plant organization shall be as shown in Figure 6.2-2 and: a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. b. At least one licensed senior operator shall be in the control room at all times during conditions other than cold shutdown or refueling.

In addition to this senior operator, at least one licensed operator or senior operator shall be present at the controls at all times when fuel is in the reactor. c. A radiation safety technician shall be on site when fuel is in the reactor.*

d. All core alterations, after the initial fuel loading, shall either be performed under the direct supervision of a licensed Senior Operator or Senior Operator holding a license limited to fuel handling.

During this time no other responsibilities shall be assigned to this individual.

e. A Fire Brigade of at least 5 members shall be maintained on site at all times.* The Fire Brigade shall not include 3 members of minimum shift crew necessary for safe shutdown or any personnel required for other essential functions during a fire emergency.
  • 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 accommodate unexpected absence provided immediate action is taken to restore the minimum requirements.

6-1 Proposed TSP0686-0104-NL04

,, ADMINISTRATIVE CONTROLS 6.2.3 FUNCTION 6.2.3.1 f. Administrative procedures shall limit the working hours of Plant staff who perform safety-related functions.

In the event that overtime is used, the 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-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 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 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). D. Except during extended shutdown periods the use of overtime should be considered on an individual basis 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.

PLANT SAFETY ENGINEERING (PSE) PSE shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety. The organization shall report to the Director of Nuclear Safety. With the concurrence of the Director, PSE may function as staff to the onsite and off site review organizations and provide technical support for problem resolution.

6-la Proposed TSP0686-0104-NL04 ADMINISTRATIVE CONTROLS COMPOSITION QUALIFICATIONS 6.2.3.3 REPORTS 6.2.3.4 6.3 6.3.1 6.3.2 6.3.3 At least three of the full-time members at the Palisades Plant shall have a bachelor's degree in engineering or a related science. At least one of the three shall.have a minimum of five years' professional experience which includes a minimum of two years' experience in nuclear power plant operation and/or design. Those individuals comprising the minimum complement of five and not having bachelor's degrees in engineering or a related science shall have at least two years' experience in the fie.ld for which they will provide expertise to PSE. Reports of PSE activities shall be submitted regularly to the NSB. PLANT STAFF QUALIFICATIONS Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.l-1971 for comparable positions.

The Plant Health Physics Superintendent shall meet or exceed the qualifications of Regul,atory Guide 1..8. September 1975.* The Shift Technical Advisor and the Shift Engineer shall have a bachelor's degree or equivalent in a or engineering discipline with specific training in plant design and/or operations.

and response and analysis of the plant for transients and accidents.

The Shift Engineer shall hold a Senior Operator License. __ *For th_e_ pt,n;pose of this section, "Equivalent," as ut:!.lized 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-lb Proposed TSP0686-0104-NL04 0\ I f\) '"'d 'i 0 'd 0 (/) Cl> p.. ' ' I EXECUTIVE VICE PRESIDENT . I EXECUTIVE MANAGER or GENERAL SERVICES I DIRECTOR OF PROPERTY PROTECTION**

I PALISADES QA DIRECTOR

  • NSB CHAIRMAN CONSUMERS POWER COMPANY OFFSITE ORGANIZATION PRESIDENT I VICE PRESIDENT EXECUTIVE VICE PRESIDENT I VICE PRESIDENT 1---ENERGY SUPPLY SERVICES NUCLEAR OPERATIONS 1 EXECUTIVE . DIRECTOR OF ENERGY SUPPLY PLANNING, TRAINING I & ADMINISTRATION OTHER EXECUTIVE PALISADES DIRECTOR<'.

SERVICES NUCLEAR GENERAL ASSURANCE MANAGER I QA DIRECTOR DIRECTOR SUPERINTENDENT NUCLEAR SAFETY* QA SUPPORT BIG ROCK POINT . **RESPONSIBLE FOR OVERALL FIRE PROTECTION PROGRAM FIGURE 6.2-1 ! ' ' : ' : I : NUCLEAR SAFETY BOARD i ! ; '.I PLANT BIG ROCK PQINT ' I I ! ' I ' ,. I ! . I e CONSUMERS POWER COMPANY PLANT ORGANIZATION NUCLEAR ASSURANCE . PLANT.

-:-:-

OFF.

---*-------GENERAL MANAGER-.(a)-

---I QA DIRECTOR ------* I I I I PLANT ENGIN.EERING AND RADIOLOGICAL TECHNICAL OPERATIONS MAINTENANCE SERVICES MANAGER (c) MANAGER MANAGER DIRECTOR I I PLANT HEAL TH PHYSICS SUPT ---(b) OPERATIONS SUPERINTENDENT(c)

I I SHIFT SUPERVISORS SRO I CONTROL AND SECOND SRO AUXILIARY ON SHIFT OPERATORS A. To support the above Plant organization, individuals knowledgeable in the following areas identified in ANSI NlS.7-1976/

ANS 3.2 will report at the discretion of the Plant General Manager: 1. Nuclear Power Plant Mechanical, Electrical and Electronic Systems 2. Nuclear Engineering

3. Chemistry and Radiochemistry
4. Radiation Protection (Reports to Health Physics Superintendent)

A single individual may be qualified and perform in more than one discipline.

  • (a)Responsible for the Plant Fire Protection Program implementation. (b)A Radiation Safety Manager (RPM as defined in Regulatory Guide 1.8) shall be designated by the Plant General Manager and shall be either the Radiological Services Manager or the Health Physics Superintendent.

The Radiation Safety Manager shall have direct access to the Plant General Manager in the matters of radiation safety. (c)Either the Plant Operations Manager or the Plant Operations dent will hold a SRO License and meet the other requirements of 6.3.1 of these Technical Specifications (as applicable to Operations Manager in ANSI Nl8.l). The indivfdual holding a SRO License shall be responsible for directing the activities of licensed operators.

TSP0686-0104-NL04 Figure 6.2-2 6-3 Proposed

  • Figure 6.2-2 (Contd) B. The Security Force will be supervised as described in the Plant Security Plan. C. Quality Assurance/Control activities will be in accordance with Consumers Power Company's Quality Assurance Program Description for Operational Nuclear Power Plants (CPC-2A, as revised).

6-3a Proposed TSP0686-0104-NL04 POSITION SS SE or SRO RO AO STA

  • Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION Power Operation, Hot Standby and Hot Shutdown l** l** 2 2 l** ) Cold. Shutdown and Refueling Shutdown*

1 None 1 2 None SS Shift Supervisor with a Senior Reactor Operators License SE Shift Engineer with a Senior Reactor Operators License SRO Individual.with a Senior Reactor Operators License RO Individual with a Reactor Operators License AO Auxiliary Operator STA Shift Technical Advisor Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 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 on-duty shift crew members provided immediate action is taken to restore the Shift -Crew Composition to within the minimum requirements of Table 6.2-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent. *Does no.t include additional personnel required when core alternations are being conducted.

See Section 6.2.2.d. **There shall be two individuals with Senior Reactor Operator licenses on shift. If the Shift Engineer is on shift, or either SRO on shift satisfies the STA qualification requirements, then the STA does not need to be stationed.

6-4 Proposed TSP0686-0104-NL04

,,

  • ADMINISTRATIVE CONTROLS 6.4 TRAINING --------*

--6;4.l* * -A retraining

  • and:. replacement training program:-*for the-plant* *E:rtaff shall be maintained under the direction of the Executive Director of Energy Supply Planning, Training and Administration, and shall meet or exceed the requirements and recommendations of Section 5.S of ANSI NlB.1-1971 and Appendix "A" of 10 CFR Part SS. 6.4.2 6.5 6.S.1 FUNCTION 6.S.1.1 6.S.1.2 ALTERNATES 6.S.1.3 The Director of Property Protection is responsible for the development, revision, approval and impiementation of the Fire Brigade training program. This training shall, as practicable, meet or exceed the requirements of Section 27 of the NFPA Code-197S.

Fire Brigade training drills shall be held at least quarterly.

REVIEW AND AUDIT PLANT REVIEW COMMITTEE (PRC) The Plant Review Committee (PRC) shall function to advise the Plant* General Manager on all matters related to nuclear safety. The PRC shall be composed of: Chairman: . Member: Member:

Member: Member: Member: Member: Member:

Member: Technical Engineer or Designated Alternate Operations Manager* Engineering and Maintenance Manager* Radiological Services Manager* Technical Director*

Reactor Engineering Superintendent Operations Superintendent Instrumentation and Control Superintendent Shift Supervisor or Shift Engineer (1) *may serve as. Designated Alternate for the Chairman Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve on 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 considered alternate members for voting purposes.

6-S Proposed TSP0686-0104-NL04

, ADMINISTRATIVE CONTROLS ----

S-.1.4-----MEETING FREQUENCY

6.5.1.5 6.5.1.6 The PRC shall meet at least once per calendar month with special meetings as required.

QUORUM A quorum of the PRC shall consist of the Chairman and four members (including alternates).

RESPONSIBILITIES The PRC shall be responsible for: a. Review of: (1) all procedures required by Specification-6.8 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Plant Generai Manager to affect nuclear safety. -b. Review of all proposed tests and experiments that affect nuclear safety. c. Review of all proposed changes to Appendix "A" Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. e. Investigation of all violations of the Technical Specifications. (A report shall be prepared covering evaluation and recommendations to prevent recurrence and forwarded to the Vice President

-Nuclear Operations and to the Director of Nuclear Safety.) f. Review of plant operations to detect potential nuclear safety hazards._

g. Performance of special reviews and investigations and reports thereof as requested by the Plant General Manager or Chairman of NSB. h. Review of the Site Emergency Plan and implementing procedures.
i. Review of all reportable events as defined in SectiQn 1.4. PRC review may be performed through a routing of the item subject to the requirements of Specification 6.5.1.7. 6-5a Proposed TSP0686-0104-NL04 ADMINISTRATIVE CONTROLS COMPOSITION

6 .5. 2. 3 * --The NsB-sha11-con:s*1st of-mem:bers appoint-ecI--by-tn-e--vi-ce Nuclear Operations.

NSB shall be chaired by the Director of Nuclear Safety who will report directly to the Vice President on Nuclear Safety Board matters. Collectively, personnel appointed for NSB shall be competent to conduct reviews in the following areas: a. Nuclear Power Plant Operations

b. Nuclear Engineering
c. Chemistry and Radiochemistry
d. Metallurgy
e. Instrumentation and Control f. Radiological Safety g. Mechanical and Electrical Engineering
h. Quality Assurance Practices An individual appointed to NSB may possess expertise in more than one of the above specialties.

These individuals should, in general, have had professional experience in their specialty at or above the Senior Engineer level. ALTERNATE MEMBERS 6.5.2.4 CONSULTANTS 6.5.2.5 Alternate members may be appointed in writing by the Vice President

-Nuclear Operations to act in place of members during any legitimate and unavoidable absences.

The qualifications of alternate members shall be similar to those of members. Consultants shall be utilized as determined by the NSB Chairman or Vice Chairman to provide expert advice to the NSB. NSB members are not restricted as to sources of technical input and may call for* separate investigation from any competent source. MEETING FREQUENCY 6.5.2.6 NSB shall meet at once per calendar quarter during the initial year of facility operation following fuel loading and at least once every six months thereafter.

6-7 Proposed TSP0686-0104-NL04 ADMINISTRATIVE CONTROLS QUORUM -6. 5-. 2 .7-----A quorcum-of---NSB--sha-11 cons-is.t---of-the Cha:irman, alternate, and at least four (4) members. No more than a minority of the quorum shall have line responsibility for operation of the facility.

It is the responsibility of the Chairman to ensure that the quorum convened for a meeting contains appropriately qualified members or has at its di°sposal consultants sufficient to carry out the review functions required by the meeting agenda. 6.5.2.8 REVIEW 6.5.2.8.1 AUDITS RESPONSIBILITIES NSB shall be responsible for the review of: a. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety. b. All reportable events and other violations (of applicable statues, codes, regulations, orders, Technical Specifications, license requirements or of internal procedures or instructions) having nuclear safety significance.

c. Issues of safety significance.

identified by the Plant General Manager, the NSB Chairman, or the PRC. d. Proposed changes in the operating license or Appendix "A" Technical Specifications.

e. The results of actions taken to correct deficiencies identified by.the audit program specified in Specifications*

6.5.2.8.2 and 6.5.2.8.3 at least once every six months. f. Safety evaluations for changes to procedures, equipment, or systems and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.

g. Maintain of PRC activities through PSE attendance at scheduled PRC meetings or through review of PRC meeting minutes. Audits of operational nuclear safety-related facility activit.ies shall be performed under the cognizance of NSB. These audits shall encompass:
a. The conformance of plant operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months. b. The performance, training and qualifications of the entire facility staff at least once per 12 months. 6-8 Proposed TSP0686-0104-NL04
  • ADMINISTRATIVE CONTROLS c. The performance of activities required by the operational quality assurance program (CPC-2A QAPD) to meet the criteria .. _ of Appendix

_10 CFR _50, _at. leas.t. once per 24 months. _ .

  • d. The Site Emergency Plan and implementing procedures at least once per 12 months. e. The Site Security Plan and implementing procedures (as required by the Site Security Plan) at least once per 12 months. f. Any other area of plant operation considered appropriate by NSB or the Vice President

-Nuclear Operations.

g. The plant Fire Protection Program and implementing procedures at least once per 24 months. h. An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified off site licensee personnel or an outside fire protection firm. i. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater *than 3 years. Audit reports encompassed by Specification 6.5.2.8.2 above shall be forwarded to the NSB Vice Chairman and Secretary, and Management positions responsible for the areas audited within thirty (30) days after completion of the audit. 6.5.2.8.3 Audits of Nuclear Operations Department shall be performed under the cognizance of the NSB. These audits shall encompass.
a. The radiological environmental monitoring program and -the results thereof at least once per 12 months. b. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months. c. The PROCESS.CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months. Audit encompassed by Specification 6.5.2.8.3 above shall be forwarded to the NSB Vice Chairman and Secretary, and Management positions responsible for the areas audited within thirty (30) days after completion of the audit. AUTHORITY 6.5.2.9 The NSB Chairman shall report to and advise the Vice President Nuclear Operations of significant findings associated with NSB activities and of recommendations related to improving plant nuclear safety performance.

6-9 TSP0686-0104-NL04 Proposed

  • ADMINISTRATIVE CONTROLS 6.9.3.1.B (Continued)

... -* -----------

*------

The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples 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 missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following:

a summary description of the radiological environmental monitoring program including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from one reactor and the results of land use censuses required by the Specification 4.11.3, and results* of the Interlaboratory Comparison Program required by Specification 4.11.5. 6-25 Proposed TSP0686-0104-NL04

  • ADMINISTRATIVE CONTROLS 6.9.3.3 Special Reports . _a. Special reports-shall be submit-ted-covering
  • the* activities identified below pursuant to the requirements of the applicable referenced specification:

Area Prestressing, Anchorage, Liner and Penetration Tests Specification Reference 4.5.4. 4.5.5 90 Days After Completion of the Test*

  • A test is considered to be complete after all associated mechanical, chemical, etc., tests have been completed.
b. Special reports shall be submitted to the Director of the NRC Region Office listed in Appendix D, 10 CFR Part 20, with a copy to the Director, Office of Inspection and Enforcement, US Nuclear Regulatory CoUDD.ission, Washington, DC 20555 within the time period specified for each report. 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated:

The following records shall be retained for at least five years: a. Records and logs of facility operation covering time interval at each power level. b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear

c.
  • All reportable events as defined in Section 1.4. d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

6-26 Proposed TSP0686-0104-NL04

  • .. ., ADMINISTRATIVE CONTROLS RECORD RETENTION (Contd) 6.10.2 _____ e. __ Records-of changes -made--to t-he-procedures--required--by

Specification 6.8.1. f. Records of radioactive shipments.

g. Records of sealed source leak tests and results. h. Records of annual physical inventory of all source material of record. The following records shall be retained for the duration of the Facility Operating License: a. Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report. b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c. Records of monthly radiation exposure for all individuals entering radiation control areas. d. Records of gaseous and liquid radioactive material released to the environs.
e. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles. f. Records of inservice inspections performed pursuant to these Technical Specifications.
g. Records of Quality Assurance activities required by the QA Program Description.
h. Records of reviews performed for changes made to procedures or equipment or reviews of tests and expetiments pursuant to 10 CFR 50.59. i. Records of meetings of the PRC and NSB. j. Records of monthly facility radiation and contamination surveys. 6-27 Proposed -TSP0686-0104-NL04 I -'---1

..J.: y

  • ADMINISTRATIVE CONTROLS k. Records of secondary water sampling and quality.** _ _ ___ __ _ . -L----Records of-the service 1-ives of a-11 hydraulic and-mechanical 6.11 6.12 6.12.1 snubbers listed on Tables 3.20.1 and 3.20.2 including the date at which the service life commences and associated installation and maintenance records. m. Records of training and qualification for members of the plant staff.** n. Records of reactor tests and experiments.**

RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR, Part 20, and shall be approved, maintained and adhered to for all operations involving personnel radia.tion exposure.

HIGH RADIATION AREA In lieu of the "control device" or "alarm signal" required by Paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem/hr but less than 1000 mrem/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit.* Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of-the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area. b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them. *Health Physics personnel or personnel escorted by Health Physics personnel 1 shall be exempt from the RWi> issuance requirement during the performance of their assigned radiation protection duties provided they comply with approved radiation protection procedures for entry into high radiation areas. **Effective with the issuance of Amendment No. 6-28 Proposed

  • " .J L
  • ADMINISTRATIVE CONTROLS RECORD RETENTION (Contd) 6.10.2 e * ---Records-of-changes -made --to--the--

proce-dure_s_

reqtilre<f by Specification 6.8.1. f. Records of radioactive shipments.

g. Records of sealed source leak tests and results. h. Records of annual physical inventory of all source material record. i. Chlorine treatment records. The following records shall be retained for the duration of the Facility Operating License: a. Record and drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report. b. _Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c. Records of monthly radiation exposure for all individuals entering radiation control areas. of d. Records of gaseous and liquid radioactive material released to the environs.
e. Records of transient or operational cycles for those-facility components designed for a limited number of transients or cycles. f. Records of inservice inspections performed pursuant to these Technical Specifications.
g. Records of Quality Assurance activities required by the QA Program Description, h. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59. i. Records of meetings of the PRC and NSB. j. Records of monthly facility radiation and contamination surveys. 6-27 Proposed TSP0686-0104-NL04 L
  • ADMINISTRATIVE CONTROLS 6.13 6.14 6.15 6.16 (Deleted) (Deleted)

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 following:

1. Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.

This program shall include the following:

1. Training of personnel,*
2. Procedures for monitoring, and 3. Provisions for maintenance of sampling and analysis equipment.

6-33 Proposed TSP0686-0104-NL04

. ' ______________

SECTION_ _ 1.0 1.1 . 1.2 -i.3 1.4 2.0 2.1 2.2 2.3 3.0 3.0 Table 2.3.1 Figure 2-1 Figure 2-2 Figure 2-3 3.1 3.1.1 Figure 3-0 3.1. 2 Figure 3-1 Figure 3-2 Figure 3-3 3.1. 3 3.1.4 3.1.5 3.1. 6 3.1. 7 3.1.8 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 TSP0686-0104A-NL04

  • PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A __ _ ____ -DESCRIPTION--

--DEFINITIONS REACTOR OPERATING CONDITIONS PROTECTIVE SYSTEMS INSTRUMENTATION SURVEILLANCE MISCELLANEOUS DEFINITIONS --------PAGE -NO ----------1-1 1-1 1-3 1-3 1-4 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 SAFETY LIMITS -REACTOR CORE SAFETY LIMITS -PRIMARY COOLANT SYSTEM PRESSURE LIMITING SAFETY SYSTEM SETTINGS -REACTOR PROTECTIVE SYSTEM Reactor Protective System Trip Setting Limits Reactor Core Safety Limits 2 Pump Operation Reactor Core Safety Limits 3 Pump Operation Reactor Core Safety Limits 4 Pump Operation LIMITING CONDITIONS FOR OPERATION APPLICABILITY PRIMARY COOLANT SYSTEM Operable Components Reactor Inlet Temperature vs Operating Pressure Heatup and Cooldown Rates Pressure -Temperature Limits for Heatup Pressure -Temperature -Limits for Cooldown Pressure -Temperature Limits for Hydro Test Minimum Conditions for Criticality Maximum Primary Coolant Radioactivity Primary Coolant System Leakage Limits Maximum Primary Coolant Oxygen and Halogens Concentrations Primary and Secondary Safety Valves Overpressure Protection Systems CHEMICAL AND VOLUME CONTROL SYSTEM EMERGENCY CORE COOLING SYSTEM CONTAINMENT COOLING STEAM AND FEEDWATER-SYSTEMS CONTAINMENT SYSTEM ELECTRICAL SYSTEMS REFUELING OPERATIONS EFFLUENT RELEASE (DELETED) i 2-1 2-3 2....:4 2-5 2-11 2-12 2-13 3-1 3-1 3-lb 3-lb 3-3a 3-4 3-9 3-10 3-11 3-12 3-17 3-20 3-23 3-25 3-25a 3-26 3-29 3-34 3-38 3-40 3-41 3-46 3-50 Proposed

___

_______ SECTION ____ _ 3.0 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 Figure 3-6 3.11 3.11.1 3.11.2 Figure 3. 11-1 3.12 3.13 3.14 3.15 3.16 Table 3.16.1 3.17 Table 3.17.1 Table 3.17.2 Table 3.17.3 Table 3.17.4 3 Table 3.18.1 3.19 3.20 Table 3.20.1 Table 3.20.2 3.21 3. 22-3. 22. l Table 3.22.1 TSP0686-0104A-NL04

  • PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A LIMITING CONDITIONS FOR OPERATION (Continued)

CONTROL ROD AND POWER DiSTRIBUTION LIMITS Shutdown Margin Requirements Individual Rod Worth Part-Length Control Rods Misaligned or Inoperable Control Rod pr Part-Length Rod Regulating Group Insertion Limits Shutdown Rod Limits Low Power Physics Testing Center Control Rod Misalignment Control Rod Insertion Limits POWER DISTRIBUTION INSTRUMENTS Incore Detectors Excore Power Distribution Monitoring System Axial Variation Bounding Condition MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY CONTAINMENT BUILDING AND FUEL STORAGE BUILDING CRANES CONTROL ROOM VENTILATION REACTOR PRIMARY SHIELD COOLING SYSTEM ENGINEERED SAFETY FEATURES SYSTEM INITIATION INSTRUMENTATION SETTINGS Engineered Safety Features System Initiation Instrument Setting Limits INSTRUMENTATION AND CONTROL SYSTEMS Instrumentation Operating Requirements for Reactor Protective System Instrumentation Operating Requirements for Engineered Safety Feature Systems Instrument Operating Conditions for Isolation Functions Instrumentation Operating Requirements for Other Safety Feature Functions SECONDARY WATER MONITORING REQUIREMENTS Secondary Water Monitoring Control Parameters IODINE REMOVAL SYSTEM SHOCK SUPPRESSORS (SNUBBERS)

Safety-Related Hydraulic Shock Suppressors (Snubbers)

Safety-Related Mechanical Shock Suppressors (Snubbers)

MOVEMENT OF SHIELDED CASK IN FUEL HANDLING AREAS FIRE PROTECTION SYSTEM Fire Detection Instrumentation Fire Detection Instrumentation

-Minimum Instruments Operable ii 3-58 3-58 3-58 3-58 3-60 3-60 3-61 3-61 3-61 3-62 3-65 3-65 3-66a 3-66d 3-67 3-69 3-70 I 3-70a _ 3-71 3-75 3-76 3-78 '3-79 3-80 3-81 3-82 3-83 3-84 3-88 3-89 3-91 3-92 3-96 3-96 3-97 Proposed

'* ' _J, "

  • PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A SECT-ION----DESGRIPTION

-3.0 3.22.2 3.22.3 3.22.4 3.22.5 LIMITING CONDITIONS FOR OPERATION (Continued)

Fire Suppression Water System Fire Sprinkler System 3.23 Fire Hose Stations Penetration Fire Barriers POWER DISTRIBUTION LIMITS Linear Heat Rate (LHR) 3.23.1 Table 3. 23. 1 Table 3.23.2 Fig. 3.23-1 Fig. 3.23-2. Fig. 3.23-3 3.23.2 3.23.3 3.24 3.24.1 Table 3.24-1 3.24.2 Linear Heat Rate Limits Radial Peaking Factor Limits, F Allowable LHR as a Function of Power Location Allowable LHR as a Function of Burnup Allowable LHR as a Function of Active Fuel Height for Interior Fuel Rods Radial Peaking Factors Quadrant Power Tilt -Tq RADIOLOGICAL EFFLUENT RELEASES Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Liquid Effluent Monitoring Instrumentation Bases for 3.24.1 Radioactive Gaseous Effluent Monitoring Instrumentation Table 3.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation Bases for 3.24.2 3.24.3 Liquid Effluents Concentration Bases for 3.24.4 Liquid Effluent Dose Bases for 3.24.4 3.24.5 Gaseous Effluents Dose Bases for 3.24.5 3.24.5.1 Dose Rate Bases for 3.24.5.1 3.24.5.2 Noble Gases Bases for 3.24.5.2 3.24.5.2 Dose -Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form Bases for 3.24.5.2 3.24.6 Gaseous Waste Treatment System Bases for 3.24.6 3.24.7 Solid Radioactive Waste Bases for 3.24.7 3.24.8 Total Dose Bases for 3.24.8 iii --.. c -PAGE NO -----3-98 3-100 3-101 3-102 3-103 3-103 3-107 3-i07 3-108 3-109 3-110 3-111 3-112 .3-114 3-114 3-115 .3-128 3-117 3-118 3-128 3-120 . 3-129 3-121 3-129 3-122 3-130 3-122 3-130 3-123 3-131 3-124 3-131 3-125 3-132 3-126 3-132 3-127 3-133 Proposed TSP0686-0104A-NL04

. '

  • PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A ---------SECTION-

DESGRIPT-ION

PAGE--NO ------4.0 SURVEILLANCE REQUIREMENTS 4-1 4.1 INSTRUMENTATION AND CONTROL 4-1 Table 4.1.1 Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System 4-3 Table 4.1.2 Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls Table 4.1.3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls 4.2 Table 4.2.1 Table 4.2.2 Table 4.2.3 4.3 Table 4.3.1 Table 4.3.2 4.4 4.5 4.5.1 4.5.2 4.5.3 4.5.4 4.5.5 4.5.6 4.5.7 4.5.8 4.6 4.6.1 4.6.2 4.6.3 4.6.4 4.6.5 4.7 4.7.1 4.7.2 4.7.3 4.8 4.9 4.10 4.11 Table 4.11-1 Table 4 .11-2 EQUIPMENT AND SAMPLING TESTS Minimum Frequencies for Sampling Tests Minimum Frequencies for Equipment Tests HEPA Filter and Charcoal Adsorber Systems SYSTEMS SURVEILLANCE Primary Coolant System Pressure Isolation Valves Miscellaneous Surveillance Items PRIMARY COOLANT SYSTEM INTEGRITY TESTING CONTAINMENT TESTS Integrated Leakage Rate Tests Local Leak Detection Tests Recirculation Heat Removal Systems Surveillance for Prestressirig System _End Anchorage Concrete Surveillance Liner Plate Surveillance Penetrations Surveillance Dome Delamination Surveillance SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS Safety Injection System Containment Spray System Pumps Valves (Deleted)

Containment Air Cooling System EMERGENCY POWER SYSTEM PERIODIC TESTS Diesel Generators Station Batteries Emergency Lighting MAIN STEAM STOP VALVES AUXILIARY FEEDWATER SYSTEM REACTIVITY ANOMALIES RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological Environmental Monitoring Program Reporting Levels for Radioactivity Concentrations in Environmental Samples

  • iv 4...:6 4-10 4-13 4-14 4-15 4-15c 4-16 4-19 4-23 4-24 4-25 4-25 4-27 4-28 4-29 4-30 4-31 4-32 4-32a 4-39 4-39 4-39 4-39 4-40 4-40 4-42 4-42 4-42 4-43 4-44 4-45 4-46 4-47 4-49 4-56 Proposed -TSP0686-0104A-NL04 I I

. ' -----------SEC'rION 4.0. Table 4 .11-3 4.11.1 4.11.3 4.11.5 4.12 4.13 4 .14 Fig. 4.12 A Fig. 4.12 B Table 4.14.1 Table 4.14.2 4.15 4.16 4.17 4.17.1 4.17.2 4.17.3 4.17.4 4.17.5 . 4.18 4.18.1 4.18.2 4.19 4.19.1 4.19.2 4.20 4.21 4.22 4.23 4.24 4.24.1 4.24.2 4.24.3 4.24.4 4.24.5 TSP0686-0104A-NL04

  • PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A -DESCRIPTION--

--SURVEILLANCE REQUIREMENTS (Continued)

Detection Capabilities for Environmental Sample Analysis Bases for Monitoring Program Bases for Land Use Census Bases for Interlaborat6ry Comparison Program AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT Augmented Inservice Inspection'Program

-Main Steam Welds Augmented Inservice Inspection Program -Feedwater Line Welds REACTOR INTERVALS VIBRATION MONITORING (DELETED)

AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS Operating Allowances Maximum Allowable Degradation PRIMARY SYSTEM FLOW MEASUREMENT INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (SNUBBERS)

FIRE PROTECTION SYSTEM Fire Detection Instrumentation Fire Suppression Water System Fire Sprinkler System Fire Hose Stations Penetration Fire Barriers POWER DISTRIBUTION INSTRUMENTATION Incore Detectors Excore Monitoring System POWER DISTRIBUTION LIMITS Linear Heat Rate Radial Peaking Factors (Intentionally Left Blank) (Intentionally Left Blank) (Intentionally Left Blank) (Intentionally Left Blank) (Intentionally Left Blank) RADIOLOGICAL EFFLUENT RELEASES Radiological Liquid Effluent Monitoring Instrumentation Radiological Gaseous Effluent Monitoring Instrumentation Liquid Effluent Concentration Liquid Effluent Dose Gaseous Effluent Dose v 4-57 4-59a 4-59a 4-59a 4-60 4-63 *4-64 4-.65 4-68 4-68d 4-69 4-70 4-7i 4-75 4-75 4-76 4-78 4-79 4-80 4-81 4-81 4-82 4-83 4-83 4-84 4-85 4-86 4-87 4-88 4-89 4-90 4-90 4-90 4-90. 4-90 4-90 Proposed I

,, '\. .... _:.. '!'-'

  • l;:a, ----*SECTION--

-4.0 4.24.6 4.24.7 4.24.8 Table 4.24-1 Table 4.24-2 Table 4.24-3 Table 4.24-5 5.0 5.1 5.2 5.2.1 5.2.2 5.2.3 5.3 5.3.1 5.3.2 5.3.3 5.4 5.4.1 5.4.2 Figure 5-1 6.0 6.1 6.2 6.2.1 6.2.2 6.2.3 6.3 6.4 Figure 6.2-1 Figure 6.2-2 Table 6.2-1 TSP0686-0104A-NL04

  • PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A ----DESCRIPTION

SURVEILLANCE REQUIREMENTS (Continued)

Gaseous Waste System Solid Radioactive Waste Total Dose Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Radioactive Liquid Waste Sampling and Analysis Program Radioactive Gaseous Waste Sampling and Analysis Program DESIGN FEATURES SITE CONTAINMENT DESIGN FEATURES Containment Structures Penetrations Containment Structure Cooling Systems NUCLEAR STEAM SUPPLY SYSTEM (NSSS) Primary Coolant System Reactor Core and Control Emergency Core Cooling System FUEL STORAGE New Fuel Storage Spent Fuel Storage Site Environment TLD Stations ADMINISTRATIVE CONTROLS RESPONSIBILITY ORGANIZATION Off site Plant Staff Plant Safety Engineering (PSE) PLANT STAFF QUALIFICATION . Consumers Power Company Offite Organization Consumers Power Company Plant Organization Minimum Shift Crew Composition TRAINING vi ---. PAGE NO --, ----4-91 4-91 4-91 4-92 4-93 4-95 "' 4-97 5-1 5-1 5-1 5-1 5-2 5-2 5-2 5-2 5-3 5-3 5-3 5-3 5-4 5-5 6-1 6-1 6-1 6-1 6-1 6-la 6-lb. II 6-2 6-3 6-4 6-5 Proposed

(_ *.o * ---------*----*-------SECTION 6.0 6.5 6. 5 .1 6.5.2 6.6 6.7 6.8 6.9 6.9.1 6.9.2 6.9.3 6.9.3.1 6.9.3.1.A 6.9.3.1.B 6.9.3.2 Table 6.9-1 6.9.3.3 6.10 6.11 6.12 6.13 6.14 6.15 6.16 6.18 6.19 6.20 6.21 TSP0686-0104A-NL04

  • * ...,_ PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS -APPENDIX A. ------------DESCRIPTION

... ------*------. '"---------PAGE--NO-

  • ------ADMINISTRATIVE CONTROLS (Continued)

REVIEW AND AUDIT Plant Review Committee (PRC) Nuclear Safety Board (NSB) (Deleted)

SAFETY LIMIT VIOLATION PROCEDURES REPORTING REQUIREMENTS Routine Reports Reportable Events Other Reporting Requirements Routine Reports Radioactive Effluent Releases Annual Radiological Environmental Operating Report Nonroutine Reports Environmental Radiological Monitoring Program Summary Special Reports RECORD RETENTION RADIATION PROTECTION PROGRAM HIGH RADIATION AREA (Deleted) (Deleted)

SYSTEMS INTEGRITY IODINE MONITORING OFFSITE DOSE CALCULATION

¥..ANUAL (ODCM) PROCESS CONTROL PROGRAM (PCP) MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS SEALED SOURCE CONTAMINATION vii 6-5 6-5 6-6a 6-10 6-10 6-10. 6-11 6-11 6-12 . 6-18 6-18 6-18 6-24 6'-25b . 6-25c 6-26 6-26 6-28 6-28 6-33 6-33 6-33 6-33 6-35 6-35 6-36 6-37 Proposed

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