Text

Amend 97 to License DPR-16,changing Tech Specs to Revise Limiting Conditions for Operation & Add Surveillance Requirements for RCS Leakage
	ML20141F645
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Site:	Oyster Creek
Issue date:	01/06/1986
From:	Zwolinski J; Office of Nuclear Reactor Regulation
To:	;
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ML20141F649	List: ML20141F645;
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	NUDOCS 8601090490
	Download: ML20141F645 (9)
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o, UNITED STATES g

NUCLEAR REGULATORY COMMISSION

E WASHINGTON, D. C. 20555

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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment'No. 97 License No. DPR-16 1.

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

A.

The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated August 23, 1985, complies with the standards and. requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.

There is reasonable assurance (1) 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 comon 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 Comission's regulations and all applicable requirements have been satisfied.

I 8601090490 860106 DR ADOCK O 29 i

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Provisional Operating License t

No. DPR-16 is hereby amended to read as follows:

L (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 97, are h:reby incorporated i

in the license. GPU Nuclear Corporation ',nall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY OMMISSION i

w John A. Zwolinski, Director BWR Project Directorate #1 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: January 6,1986 1

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ATTACHMENT TO LICENSE AMENDMENT NO. 97 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 i

Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.

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REMOVE INSERT i

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11 ii 1.0-6 1.0-6 3.3-la 3.3-2 3.3-2 3.3-5 3.3-5 4.3-2 4.3-2

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TABLE OF CONTENTS

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L Section 1 Definitions Page 1.1 Operable

1. 0-1 1

1.2 Operating

1. 0-1 j

1.3 Power Operation 1.0-1 1.4 Startup Mode

1. 0-1 1.5 Run Mode 1.0-1 l

1.6 Shutdown Condition

1. 0-1 l

1.7 Cold Shutdown

1. 0-1 i

1.8 Place in Shutdown Condition 1.0-2 1.9 Place in Cold Shutdown Condition 1.0-2 1.10 Place in Isolated Condition 1.0-2 1.11 Refuel Mode 1.0-2 1.12 Refueling Outage 1.0-2 l

1.13 Primary Containment Intagrity 1.0-2 i

1.14 Secondary Containment Integrity 1.0-2 1.15 Deleted 1.0-3 l.16 Rated Flux 1.0-3 j

1.17 Reactor Thermal Power-to-Water 1.0-3 1.18 Protective Instrumentation Logic Definitions 1.0-4 1.19 Instrumentation Surveillance Definitions 1.0-4 I

1.20 FDSAR 1.0-4 1.21 Core Alteration 1.0-5 i

1.22 Minimum Critical Power Ratio 1.0-5 1.23 Staggered Test Basis 1.0-5 i

1.24 Surveillance Requirements 1.0-5 i

1.25 Fire Suppression Water System 1.0-5 l.26 raction of Limiting Power Density (FLPD) 1.0-6 1.27 Maximum Fraction of Limiting Power Density (MFLPD) 1.0-6 1.28 Fraction of Rated Power (FRP) 1.0-6 2

l.29 Top of Active Fuel (TAF) 1.0-6 1.30 Reportable Event 1.0.6 1.31 Identified Leakage 1.0-6 1.32 Unidentified Leakage 1.0-6

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t Section 2 Safety Limits and Limiting Safety System Settings 2.1 Safaty Limit - Fuel Cladding Integrity 2.1 -1 2.2 Safety Limit - Reactor Coolant System Pressure

2. 2-1 i

2.3 Limiting Safety System Settings 2.2-3 Section 3 Limiting Conditions for Operation 3.0 Limiting Conditions for Operation (General)

3. 0-1 3.1 Protective Instrumentation 3.1.1 3.2 Reactivity Control 3.2-1 1

3.3 Reactor Coolant

3. 3-1 3.4 Emergency Cooling 3.4-1

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I Amendment No. H, 84,97

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TABLE OF CONTENTS (cont'd) 3.5 Containment

3. 5-1 3.6 Radioactive Effluents

3. 6-1 3.7 Auxiliary Electrical Power

3. 7-1 3.8 Isolation Condenser

3. 8-1 3.9 Refueling

3. 9-1 3.10 Core Limits 3.10-1 3.11 (Not Used) 3.11-1 3.12 Fire Protection 3.12-1 3.13 Accident Monitoring Instrumeritation 3.13-1 Section 4 Surveillance Requirements 4.1 Protective Instrumentation 4.1 -1 4.2 Reactivity Control 4.2-1 4.3 Reactor Coolant

4. 3-1 4.4 Emergency Cooling

4. 4-1 4.5 Containment

4. 5-1 4.6 Radioactive Effluents

4. 6-1 4.7 Auxiliary Electrical Power 4.7-1 4.8 Isolation Condenser 4.8-1 4.9 Refueling 4.9-1 4.10 ECCS Related Core Limits.

4.10-1 4.11 Sealed Source Contamination 4.11-1 4.12 Fire Protection 4.12-1 4.13 Accident Monitoring Instrumentation 4.13-1 Section 5 Design Features 5.1 Site 5.1 -1 5.2 Containment

5. 2-1 5.3 Auxiliary Equipment 5.3-1 Section 6 Administrative Controls 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Facility Staff Qualifications 6-5 6.4 Training 6-7 6.5 Review and Audit 6-8 6.6 Reportable Event Action 6-14 6.7 Safety Limit Violation 6-15 6.8 Procedures 6-15 6.9 Reporting Requirements 6-16 6.10 Record Retention 6-22 6.11 Radiation Protection Program 6-23 6.12 (Deleted) 6.13 High Radiation Area 6-24 6.14 Environmental Qualification 6-24*

6.15 Integrity of Systems Outside Containment 6-25 6.16 Iodine Monitoring 6-25

Issued by NRC Order dated 10-24-80 l

11 Amendment No. 54, 59, 84,97 l

1.0-6 1.26 FRACTION OF LIMITING POWER DENSITY (FLPD)

The fraction of limiting power density is the ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR for that bundle type.

1.27 MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD)

The maximum fraction of Ifmiting power density is the hignest value existing in the core of the fraction of limiting power density (FLPD).

1.28 FRACTION OF RATED POWER (FRP)

The fraction of rated power is the ratio of core thermal power to rated thermal power.

1.29 TOP OF ACTIVE FUEL (TAF) - 353.3 inches above vessel zero.

1.30 REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.

l.31 IDENTIFIED LEAKAGE IDENTIFIED LEAKAGE is that leakage which is collected in the primary containment equipment drain tank and eventually transferred to radwaste for processing.

1.32 UNIDENTIFIED LEAKAGE UNIDENTIFIED LEAKAGE is all measured leakage that is other than identified leakage.

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l Amendment No. 75, 84, 97 y--3

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3.3-la i

D.

Reactor Coolant System Leakag?

1.

Reactor coolant system leakage shall be limited to:

a.

5 gpm unidentified leakage i

b.

25 gpm total (identified and unidentified) c.

2 gpm increase in unidentfied leakage rate within i

any 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period while operating at steady state power 2.

With the reactor coolant system leakage greater than the limits in 3.3.D.1.a or b above, reduce the leakage rate to witnin the acceptable limits within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or place the reactor in the shutdown condition within the next 12 I

hours and he in the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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3.

With any reactor coolant leakage greater than the limit in 3.3.D.1.c above, identify the source of leakage within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or be in the shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and be in the cold shutdown condition within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

For determination of unidentified leakage, the primary containment sump flow monitoring system shall be operable except as specified below:

a.

With the primary containment sump flow integrator inoperable:

1.

Restore it to operable status within 7 days.

2.

Calculate the unideqtified leakage rate utilizing an acceptable alternate means as specified in plant procedures.

b.

If Specification 3.3.D.4.a cannot be met, place the reactor in the shutdown condition within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

5.

For determination of identified leakage, the primary containment equipment drain tank monitoring system shall be operable except as specified below.

a.

With the primary containment equipment drain tank monitoring system inoperable:

i 1.

Restore it to operable status within 7 days.

2.

Calculate the identified leakage rate utilizing an acceptable alternate means as specified in plant procedures.

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b.

If Specification 3.3.D.5.a cannot be met, place the reactor in the shutdown condition within the next l

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l Amendment No. 97 i

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3.3-2 I

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Weactor Coolant Quality 1.

The reactor coolant quality during power operation with steaming rates to the turDine-condenser of less than 100,000 pounds per hour shall be l

limited to:

conductivity 2 uS/cm (S = mhos at 25 C(77 F))

l chloride ion 0.1 ppm j

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When the conductivity.and chloride concentration limits given in 3.3.E.1 are exceeded, an orderly shutdown shall be initiated j

immediately, and the reactor coolant temperature shall be reduced to less than 212*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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The reactor coolant quality during power operation with steaming rates j

to the turbine-condenser of greater than or equal to 100,000 pounds

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per hour shall be limited to:

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conductivity 10 uS/cm (S = mho's at 25 C(77 F))

i chloride ton 0.5 ppm l

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When the maximum conductivity or chloride concentration limits given f

in 3.3.E.3 are exceeded, an orderly shutdown shall be initiated innediately, and the rengtor coolant temperature shall be I

reduced to less than 212 F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

5.

During power operation with steaming rates to the turbine-condenser of greater than or equal to 100,000 pounds per hour, the time limit above l

1.0 uS/cm at 25'C (77'F) and 0.2 ppe chloride shall not exceed 72 l

hours for any single incident.

7 When the tim' limits for 3.3.E.5 are exceeded, an orderly shutdown i

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e shall be initiated within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

F.

Recirculation 1.oop Operability l

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The reactor shall not be operated with one or more recirculation loops out of service except as specified in Specification 3.3.F.2.

2.

Reactor Operation with one idle recirculation loop is permitted l

provided that the idle loop is not isolated from the* reactor vessel.

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If Specifications 3.3.F.1 and 3.3.F.2 are not met, the reactor shall j

i be placed in the cold shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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i Amendment lie. N, 33,97

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3.3-5

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The drywell floor drain sump and eggjpment drain tank provide the primary means of leak detectionL9.Wl.

Identified leakage is that from valves and pumps in the reactor system and from the reactor vessel head flange gasket. Leakage through the seals of this equipment is piped to the drywell equipment drain tank. Leakage from other sources is classified as unidentified leakage and is collected in the drywell floor drain sump. Leakage which does not flash in a vapor will drain in the sump. The vapor will be condensed in the drywell ventilation system and routed to the sump.

Condensate cannot leave the sump or the drywell equipment drain tank unless the respective pumps are running. The sump and the drain tank are provided with two pumps each. Alams are prov for the sump that will actuate on a predetemined pumpout rate gL J and will be set to actuate at a leakage that is less than the unidentified leakage limit of 5 gpe.

Additional qualitative infomation (10) is available to the operator via the monitored drywell atmospheric condition. However,

.this infomation is not quantitative since fluctuation in i

atmospheric conditions are nomally expected, and quantitative l

measurements are not possible. The temperature of the closed l

cooling water which serves as coolant for the drywell ventilation i

system is monitored and also provides infopption which can be related to reactor coolant system leakage tW.

Additional protection is provided by the drywell high pressure scram which would be exgd to be reached within 30 minutes of a steam leak of about 12 gpa 4

During a loss of offsite AC power, the control rod drive hydraulic

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pumps, which are powered by the diesels, each can supply 110 gpm water makeup to the reactor vessel. A 25 gpm limit for total l

leakage, identified and unidentified, was establisned to be less than the 110 gpm makeup of a single rod drive hydraulic pump to avoid the use of the emergency core cooling system in the event of a l

loss of normal AC power.

Materials in the primary system are primarily 304 stainless steel i

i and zircaloy fuel cladding. The reactor water chemistry limits are placed upon conductivity and chloride concentration since conductivity is measured continuously and gives an indication of i

abnormal conditions or the presence of unusual materials in the coolant, while chloride limits are specified to prevent stress corrosion cracking of stainless steel.

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Amendment No. 97 i

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ML20141F645

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