Text

Amend 122 to License DPR-20,revising Tech Specs to Require Specific Alternate Shutdown Sys Equipment & Instrumentation to Be Operable Whenever Reactor Coolant Temp at or Above 325 F
	ML20247J175
Person / Time
Site:	Palisades
Issue date:	05/19/1989
From:	Yandell L; Office of Nuclear Reactor Regulation
To:	;
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	NUDOCS 8906010062
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'o, UNITED STATES

'8 NUCLEAR REGULATORY COMMISSION o

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e WASHINGTON, D. C. 20665 CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 122

-License No. 0PR-20 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Consumers Power Company (the licensee) dated November 21, 1985 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 l

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 anendment will not be inimical to the common defense and security or to the health and safety of the public; and l

E.

The issuance of this amendment is in accordance with 10 CFR Part 51~

of the Commission's Regulations and all applicable requireruts have been satisfied.

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 l

I amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 122, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

l 8906010062 890519 ADOCK0500gg5 PDR P

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3.

This 'licen:;e amendment is effective as of, the date of its issuance and shall be implemented not later than July 3,1989,

FOR THE NUCLEAR REGULATORY COMMISSION GJt011oQ QAgN iwrence A. Yaiidell,' Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V

& Special Projects Office of Nuclear Reactor Regulation

Attachment:

~ Changes to the Technical Specifications Date of. Issuance: May 19, 1989

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' ATTACHMENT TO LICENSE AMENDMENT NO.122 PROVISIONAL OPERATING LICENSE NO. DPR-20 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 iii iii v

v 3-134 3-135 3-136 4-85 4-85 4-86 4-87 4-88 e

I FALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE N0 3.0 LIMITING CONDITIONS FOR OPERATION (Continued) l 3.22.2 Fire Suppression Water System 3-98 3.22.3 Fire Sprinkler System 3-100 3.22.4 Fire Hose Stations 3-101 3.22.5 Penetration Fire Barriers 3-102 3.23 POWER DISTRIBUTION LIMITS 3-103 3.23.1 Linear Heat Rate (LHR) 3-103 Table 3.23.1 Linear Heat Rate Limits 3-107 Table 3.23.2 Radial Peaking Factor Limits, F 3-107 Fig. 3.23-1 AllowableLHRasaFunctionofheakPowerLocation 3-108 Fig. 3.23-2 Allowable LHR as a Function of Burnup 3-109 Fig. 3.23-3 Allowable LHR as a Function of Peak Power Location for Interior and Narrow Water Gap Fuel Rods 3-110 3.23.2 Radial Peaking Factors 3-111 3.23.3 Quadrant Power Tilt - Tg 3-112 3.24 RADIOLOGICAL EFFLUENT RELEASES 3-114

-f 3.24.1 Radioactive Liquid Effluent Monitoring Instrumentation 3-114 Table 3.24-1 Radioactive Liquid Effluent Monitoring Instrumentation 3-115 Bases for 3.24.1 3-128 3.24.2 Radioactive Gaseous Effluent Monitoring Instrumentation 3-117 Table 3.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation 3-118 Bases for 3.24.2 3-128 3.24.3 Liquid Effluents Concentration 3-120 Bases for 3.24.3 3-129 3.24.4 Liquid Effluent Dose 3-121 Bases for 3.24.4 3-129 3.24.5 Gaseous Effluents Dose 3-122 Bases for 3.24.5 3-130 3.24.5.1 Dose Rate 3-122 Bases for 3.24.5.1 3-130 3.24.5.2 Noble Gases 3-123 Bases for 3.24.5.2 3-131 3.24.5.3 Dose - Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form 3-124 i

{

Bases for 3.24.5.3 3-131 3.24.6 Gaseous Waste Treatment System 3-125 Bases for 3.24.6 3-132 i

3.24.7 Solid Radioactive Waste 3-126 Bases for 3.24.7 3-132 3.24.8 Total Dose 3-127 Bases for 3.24.8 3-133 3.25 ALTERNATE SHUTDOWN SYSTEM 3-134 Table 3.25.1 Alternate Shutdown Minimum Equipment 3-135 iii Amendment No. 37, 45, $3, 67, (E, E5, 19E.122

)

1

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE N0 4.0 SURVEILLANCE REQUIREMENTS (Continued)

Table 4.11-3 Detection Capabilities for Environmental Sample,

Analysis 4-57 4.11.1 Bases for Monitoring Program 4-59a 4.11.3 Bases for Land Use Census 4-59a 4.11.5 Bases for Interlaboratory Comparison Program 4-59a 4.12 AUGMENTID INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT 4-60 Fig. 4.12 A Augmented Inservice Inspection Program - Main Steam Welds 4-63 Fig. 4.12 B Augmented Inservice Inspection Program - Feedwater Line Welds 4-64 4.13 REACTOR INTERNALS VIBRATION MONITORING (DELETED) 4-65 4.14 AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS 4-68 Table 4.14.1 Operating Allowances 4-68d Table 4.14.2 Maximum Allowable Degradation 4-69 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 4.17.1 Fire Detection Instrumentation 4-75 4.17.2 Fire Suppression Water System 4-76 4.17.3 Fire Sprinkler System 4-78 4.17.4 Fire Hose Stations 4-79 4.17.5 Penetration Fire Barriers 4-80 4.18 POWER DISTRIBUTION INSTRUMENTATION 4-81 4.18.1 Incore Detectors 4-81 4.18.2 Excore Monitoring System 4-82 4.19 POWER DISTRIBUTION LIMITS 4-83 4.19.1 Iinear Heat Rate 4-83 4.19.2 Radial Peaking Factors 4-84 4.20 MODERATOR TEMPERATURE COEFFICIENT (MTC) 4-85 4.21 ALTERNATE SKUTDOWN SYSTEM 4-86 Table 4.21.1 Alternate Shutdown System Montoring Instrumentation Surveillance Requirements 4-87 4.22 (Deleted) 4.23 (Deleted) 4.24 RADIOLOGICAL EFFLUENT RELEASES 4-90 4.24.1 Radiological Liquid Effluent Monitoring Instrumentation 4-90 4.24.2 Radiological Gaseous Effluent Monitoring Instrumentation 4-90 4.24.3 Liquid Effluent Concentration 4-90 4.24.4 Liquid Effluent Dose 4-90 f,t 4.24.5 Gaseous Effluent Dose 4-90 1

v Amendment No. 37,45,53,67,SE,E5, 1

JRE, JJE,122 i

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3.25 ALTERNATE SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.25.1 The Alternate Shutdown System instrumentation and components shown in Table 3.25.1 shall be OPERABLE. Operability shall be demonstrated by performing the surveillance in accordanc,e with Section 4.20.

APPLICABILITY:

Reactor coolant temperature > 325*F.

ACTION:

With less than the " Minimum Equipmer.t" in Table 3.25.1 Operable, a.

restore the inoperable equipment to Operable within 7 days, or provide equivalent shutdown capability and restore the inoperable equipment to Operable within 60 days; or be in Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Cold Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

The provisions of Specification 3.0.3 and 3.0.4 do not apply.

Basis The operability of the Alternate Shutdown System ensures that any fire will not preclude achieving safe shutdown. The Alternate Shutdown System components are independent of areas where a fire cculd damage systems normally used to shut down the reactor. This capability is consistent with Regulatory Guide 1.97 and Appendix R to 10CFR50.

3-134 Amendment No.122

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Table 3.25.1 ALTERNATE SHUTDOWN MINIMUM EQUIPMENT l

d Minimum Readout No Instrumentation Equipment Location,

1 Pressurizer Pressure 1

C150 (PI-0110) 2 Pressurizer Level 1

C150 (LI-0102E) 3 Reactor Coolant Hot Leg.

1/ Loop C150A.

Temperature (TI-0112HAA)

(TI-0122HAA) 4 Reactor Coolant Cold Leg 1/ Loop C150A Temperature l

(TI-0112CAA)

(TI-0122CAA) 5 Steam Generator Pressure 1/S.G.

C150A (PI-0751E)

)

(PI-0752E)

~

6 Steam Generator Level 1/S.G.

C150 (LI-0757C)

(LI-0758C) f

g 7

Start-up Range Neutron 1

C150A Monitor (N-001A) 8 Auxiliary Feedwater 1

C150 Suction Pressure (PS-0741D) f 9

SIRW Tank Level 1

C150A (LT-0332B) f f

10 Auxiliary Feedwater 1/S.G.

C150 Flow Rate (FI-0727B)

/

(FI-0749B)

/

3-135 Amendment No. 122

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Table 3.25.1 (Continued)

ALTERNATE SHUTDOWN MINIMUM EQUIPMENT f

Transfer Minimum Switch No Switches Equipment Location Function f

II HS-0102A 1

C150 Control Room Alarm 12 HS-0102B 1

C150 S/G Level Indications

/

Pressurizer Level Indications Aux. W Flow Indication Aux. W Flow Control 13 HS-0522C C150 Opens Aux. W Pump Steam

/

Valve CV-0522B 14 HS-0102C 1

C150A Control Room Alarm

/

S/G Pressure Indications

/

Hot / Cold Leg Temperature

/

Indications

/

f f

Minimuin Controls

/

No Control Circuits Equipment From Function

/

IS Auxiliary W Flow 1

C150 Controls B S/G Control (HIC-0727C)

Aux W Flow Control

/

Valve (CV-0727) 16 Auxiliary W Flow 1

C150 Controls A S/G

/

Control (HIC-0749C)

Aux. W Flow Control Valve (CV-0749) i i

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3-136 Amendment No. 122

4.20 MODERATOR TEMPERATURE COEFFICIENT (MTC)

SURVEILLANCE REQUIREMENTS 4.20.1 The MTC shall be determined to be within its limits by-confirmatory measurements prior to initial operation above 2%

of rated thermal power, after each refueling.

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4-85 Amendment No.85,115,122 e

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4.21 ALTERNATE SHUTDOWN SYSTEM SURVEILLANCE REQUIREMENTS 4.21.1 Each alternate shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performing a channel check and a channel calibration per Table 4.21.1.

4.21.2 Each alternate shutdown system transfer switch and control circuit shall be demonstrated OPERABLE by operating each activated component from the alternate shutdown panel, et least once per refueling cycle.

.j-e 4-86 Amendment No. 122

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