ML20202B740

Amend 193 to License DPR-16,extending Instrumentation Surveillances for Condenser Low Vacuum,High Temp Main Steamline Tunnel,Recirculation Flow & Reactor Coolant Leakage

ML20202B740
Person / Time
Site:	Oyster Creek
Issue date:	11/26/1997
From:	Zwolinski J NRC (Affiliation Not Assigned)
To:
Shared Package
ML20202B745	List: ML20202B740
References
NUDOCS 9712030168
Download: ML20202B740 (9)

Text

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UNITED STATES g

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NUCLEAR REGULATORY COMMISSION p

WASHINGTON, D.C. t004H001

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GPU NUCLEAR CORPORATION j

m JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 License No. DPR-16 1.

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

A.

The application for amendment by GPU Nuclear Corporation, et al.

(the licensee), dated October 10, 1996, as supplemented March 25, June 6, and August 29, 1997, 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 j

Comission; C.

There is reasonable assurance (i) that tho activities authorized l

by this amendment can be conducted without endangriag the health and safety of the public, and (ii) that such activ:hss 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 sa'atv of the public; and l

E.

The issuance of this amendment is in accordance with li l

Part 51 of the Comission's regulations and all applica..

requirements have been satisfied.

9712030168 971126 PDR ADOCK 05000219 P

PDR

- 2.

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

(2)

Jechnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.193, are hereby incorporated in the license.

GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION John A. Zwolinski, eputy Director l

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i

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Attachment:

Changes to the Technical i

Specifications l

Date of Issuance: November 26, 1997 l

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ATT5CHMEN1 T0' LfCENSE" AMINDM'ENT NO.193 FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A. Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 4.1-4 4.1-4 4.1-5 4.1-5 4.1-7 4.1-7 4.3-2 4.3-2 4.4-1 4.4-1 4.5-4 4.5-4

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l TABLE 4.1.1 (Cont'd.)

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i MINIMUM CHECK. CAU,RM'l]DN AND TEST FREOUENCY FOR PRDTECTIVE INSTRUMENTATION i

instrument Channel ChCf& Calibrate Ten Remarks (Anolles to Test and l

Calibration) i

13. DEL CTED l

5

14. High Radiation in Reactor Building Operating Floor 1/s 1/3 mo 1/3 mo Using gamma source for Ventilation Exhaust 1/s 1/3 mo 1/3 mo calibration

15. High Radiation on 1/3 mo 1/3 mo Using built-in calibration Air Ejector Off Gas equipment

+

1/s Channel Check l

1/mo Source check 1/24 mo Calibmtion according to established station calibration procedures 1/24 mo Note a -

16. IRM level N/A Each N/A startup IRM Scram Usir:g built-in calibration equipment

17. IRM Blocks N/A Prior Prior Upscale and downscale to to startup startup aM aM shutdown shutdc.vn

18. Condenser Low N/A 1/24 mo 1/24 mo Vacuum

19. Manual Scram Buttons N/A N/A 1/3 mo

20. High Temperature Main -

N/A 1/24 mo Each Using heat source box

-Steamline Tunnel refueling outage

- OYSTER CREEK 4.14 Amendment No.: 71,100,141,10^,171 193

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TABLE 4.1.1 (cont'd) 1 Instrument Chantal Qg;k Calibrate Igg Remarks (Anolies to Test and 1

Qlibration) l l

Using built in calibration

21. SRM equipment

22. Isolation Condenser High Flow N/A 1/3 mo 1/3 mo By application of l

AP (Seam and Water) test pressure

23. Turbine Trip Scram N/A N/A 1/3 mo

24. Generator land Rejection N/A 1/3 mo 1/3 mo Scram

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25. Recirculation loop Flow N/A 1/24 mo N/A By application of test pressure

26. Law Reactor Pressure Core N/A 1/3 mo 1/3 mo By application of test Spray Valve Permissive pressure 1

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37. Scrum Discharge Volume i

(Rod Block) l a) Water level N/A Each re-1/3 mo Calibrate by varying level high fueling in sensor column L

cutage b) Scram Trip N/A N/A Each re-bypass fueling

(

outage l

28. less of Power i

a) 4.16 KV 1/d 1/24 mo 1/mo Emergency Bus i

Undervoltage l

(loss of voltage) b) 4.16 KV 1/d 1/24 mo 1/mo Emergency Bus L_

Undervoltage _

(Degraded Voltage) 1 OYSTER CREEK 4.15 Amendment No.: 14.171193 b

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TABLE 4.1.2

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MINIMUM TEST FREOUENCIES FOR TRIP SYSTEMS Trio System Minimum Test Freauency 1)

Qual Channel (Scram)

Same as for respective instrumerotlon in Table 4.1.1 l

2)

Rod Block Same as for respective instrumentation in Table 4.1.1 3)

DELLTED DELETED 4)

AutQmatic Deoressurization Each refueling outage each trip system, one at a time

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5)

MllV Closure, each closure Each refueling outage logic circuit irxicpendently (1 valve at a time) 6)

Core _ Spray, each trip 1/3 mo and each refueling outage system, one at a time 7)

Primary Containment Each refueling outage Isolation, each closure cin: ult independently (1 valve at a time) 8)

Refueline Interlocks Prior to each refueling operation 9)

Isolation Condenser Actuation Each refueling outage and Isolation, each trip circuit independently (1 valve at a time)

10) Reactor Buildinc IsolatioD Same as for respective and SGTS Initiation instrumentation in Table 4.1.1

-11) Condenser Vacuum Pumn Prior to ea:h startup Isolation

12) Air Elector Offeas Line Isolation Each refueling outage

13) Containment Vent and Purce 1/24 mo isolation OYSTER CREEK 4.17 Amendment No. 108, 115, 144, 100, 171 193 1

4.4 EMERGENCY COOI.ING Apolicability: Applies to surveillance requirements for the emergency cooling systems.

Obiective: To verify the operability of the emergency cooling systems.

Sgtgification: Surveillance of the emergency cooling systems shall be periamed as follows:

hcm Freauency A.

Core Sorav System

1. Pump Operability Once/ month. Also after major maintenance and prior to startup following a refueling outage.

2. Motcr operated valve Once/ month operability

3. Automatic acuation test Every three months

4. Pump compartment water.

Once/ week and after each entry tight doors closed

5. Core spray header AP instrumentation check Once/ day calibrate Once/3 months test Once/3 months B.

Automatic Deoressurization

1. Valve operability Once every 24 montits*

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2. Automatic actuation test Every refueling outage C.

Containment Coolinc System l

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1. Pump Opembility Once/ month. Also after major maintenance and

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prior to startup following a refueling outage.

l CValve operability shall be demons: rated at system operating pressure prior to exceeding 5 percent power, following a refueling outage.

OYSTER CREEK 4.4 1 Amendment No. 109,144 193

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O.

Primary Caalant System Pram lealmtlan Valves Caacifalon:

I 1,

Periodic leakage testing ) on each valve listed in Table 4.3.1 shall be accomplished prior to exceeding 600 psig reactor pressure every

- time the plant is placed in the cold shutdown condition for refueling, each time the plant is placed in a cold shuidown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, whenever the valve is moved whether by manual actuation or due to flow conditions, and after returning the valve to service after maintenance, repair or replacement work is performed.

H.

P=ctor Caalant Svinem 1 -kaa.

1.

Unidentified leakage rate shall be calculated at least onw every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2.

Total leakage rate (identified and unidentired) shall be calculated at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

3.

A channel calibration of the primary containment sump flow integrator and the prirnary containment equipment drain tank flow integrator shall be conducted at least once per 24 months.

1.

An inservice inspection program fer piping identified in NRC Generic letter 88-01 shall be performed in accordance with the NRC staff positions on schedule, methods, personnel, and sample expansion included in the generic letter or in accordance with alternate measures approved by the NRC staff.

Bass Data is available relating neutron fluence (E>l.0MeV) and the change in the Reference Nil Ductility Transition Temperature (RTer). The pressure temperature (P-T) operating curves A,B,and C in Figures 3.3.1.3.3.2,and 3.3.3 wre develogod ta*d m tJe results of tating and evalmtim of specians rmoved fmn tJe vesm1 after 8.38 DTY of oteratim. Sindlar testing and analysis will te terfomvl thmshmt vosm1 life to mnitor tJe effects of neutron irradiatim m tJe rector vessel dell mterials.

'Ihe inspection program will reveal problem areas should they occur, before a leak develops. In addition, extensive visual inspection for leaks will be made on critical systerns. Oyster Creek was designed and constructed pnor to

To satisfy ALARA requirements, leakage may be measured -

indirectly (as from the performance of pressure indicators) if

. accomplished in accordance with approved procedures and supponed by computations shwing that the method is capable of demonstratmg valve compliance with the leakage criteria.

• NRC Order dated April 20,1981.

OYSTER CREEK -

4.3-2 Amendment No. 07,110,120,1 1,1;,,18s,193 l

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(3) At least four of the suppression chamber - drywell vacuum breakers shall be inspected, if deficiencies are found, all vacuum breakers shall be inspected and deficiei :les corrected such that Specification C

3.5.A.5.a can be met.

(4) A drywell to suppression chamber leak rate test shall be performe<l once every 24 months to demonstrate, that with an initial differential pressure of not less than 1.0 psi, the differential pressure decay rate shall not exceed the equivalent of air flow through a 2 inch orifice.

G.

Reactor Building 1.

Secondary containment capability tests shall be conducted after isolating the reactor builc'ing and placing either Standby Gas Treatment System tilter train in operation.

2.

De tests shall be performed at least once per operating cycle (interval not to exceed 20 months) and shall demonstra'e the capability to maintain a % inch of water vacuum under calm wind conditions with a Standby Gas Treatment System Filter train flow rate of not more than 4000 cfm.

3.

A secondary containment capability test shall be conducted at each tefueling outage prior to refueling.

4.

The results of the secondary contalrtment capability tests shall be in the subject of a summary technical report which can be Niuded in the reports specified in Section 6.

11.

Standby Gas Treatment System 1.

The capability of each Standby Gas Treatment System circuit shall be demonstrated by:

a.

At least once per 18 months, after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation, and following significant painting, fire, or chemical release in the reactor building during operation of the Standby Gas Tiratment System by verifying that:

(1) The charcoal absorbers remove 299% of a halogenated hydrocarbon refrigerant test gas and the 11 EPA filters remove.>_99% of the DOP in a cold DOP test when tested in accordance with ANSI N510-1975.

OYSTER CREEK 4.5-4 Amendment No.. 144,105,193