ML20137X098

Amend 190 to License DPR-16,modifying TS by Replacing Description of Existing Permissive Interlock from AC Voltage to Core Spray Booster Pump Differential Pressure Permissive Greater than 21.2 Psid

ML20137X098
Person / Time
Site:	Oyster Creek
Issue date:	04/14/1997
From:	Milano P NRC (Affiliation Not Assigned)
To:
Shared Package
ML20137X103	List: ML20137X098 ML20137X107
References
NUDOCS 9704210160
Download: ML20137X098 (7)

Text

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4 UNITED STATES g

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20666 4 001 GPU NUCLEAR CORPORATION A!Q JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 190 License No. DPR-16 1.

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

A.

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

(the licensee), dated October 10, 1996, 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 (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 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.

i 9704210160 970424 yDR ADOCK 05000219 PDR g

. 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)

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.190, 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 Fatrick D. Milano, Acting Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specific'ations i

Date of Issuance: April 14, 1997

)

I ATTACHMENT TO LICENSE AMENDMENT NO. 190 FACILITY OPERATING LICENSE N0. 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.

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Remove Insert 3.1-11 3.1-11 3.1-16 3.1-16 3.1-16a 4.1-6 4.1-6 i

O D

TABLE 3.1.1 PROTECTIVE INSTRUMENTATION REQUIREMENTS Reactor Modes Min. No. of Min. No. of in which Function OPERABLE or Instrument Must Be OPERABLE OPERATING Channels Per Trip

[ tripped]

OPERABLE Action Eunction Setting Shutdown Refuel Startuo Run Trio Systems Trio System Reauired*

D. Core Sorav Consider the respective

1. Low-Low X(t)

X(t)

X(t)

X 2

2(pp) core spray Reactor Water Level loop inoperable,

2. High Drywell 5 3.5 psig X(t)

X(t)

X(t) X 2(k) 2(k)(pp) and comply Pressure with Spec. 3.4

3. LowReactor 2 285 psig X(t)

X(t)

X(t) X 2

2(pp)

Pressure (valve pennissive)

E. Containment Sorav 4

]

Comply with Technical Specification 3.4 F. Primary Containment Isolation J. High Drywell

$ 3.5 psig X(u)

X(u)

X(u) X 2(k) 2(k)(oo) Isolate Pressure containment or PLACE IN

2. Low-Low 2 7'2" above X(u)

X(u)

X(u) X 2

2(oo)

COLD SHUT-Reactor Water TOP OF DOWN Level ACTIVE FUEL CONDITION 6

G. Automatic Deoressurization

1. High Drywell

< 3.5 psig X(v)

X(v)

X(v) X 2(k) 2(k)

See note h.

Pressure

2. Low-Low-Low 2 4'8" above X(v)

X(v)

X(v) X 2

2 See note h.

Reactor Water TOP OF Level ACTIVE FUEL

3. Core Spray Booster Pump d/p Permissives: > 21.2 psid X(v)

X(v)

X(v) X note i.

note i.

See note i.

OYSTER CREEK 3.1-11 Amendment No.: 44,79,112,160,171,.190 Change 4; Correction: 5/11/84

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^

TABLE 3.1.1 (CONTD)

Act!on required when minimum conditions for operation are not satisfied. Also permissible to trip inoperable trip system. A channel may be placed in an inoperable status for up to six hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE instrument channel in the same trip system is monitoring that parameter.

See Specification 2.3 for Limiting Safety System Settings.

Noter Permissible to bypass, with control rod block, for reactor protection system reset in REFUEL MODE.

a.

b.

Permissible to bypass below 800 psia in REFUEL and STARTUP MODES.

One (1) APRM in each OPERABLE trip system may be bypassed or inoperable provided the c.

requirements of Specification 3.1.C and 3.10.C are satisfied. Two APRMs in the same quadrant shall not be concurrently bypassed except as noted below or permitted by note.

Any one APRM may be removed from service for up to six hours for test or calibration without inserting trips in its trip system only if the remaining OPERABLE APRMs meet the requirements of Specification 3.1.B 1 and no control rods are moved outward during the calibration or test. During this short period, the requirements of Specifications 3.1.B.2,3.1.C and 3.10.C need not be met.

d.

The IRMs shall be inserted and OPERABLE until the APRMs are OPERABLE and reading at least 2/150 full scale.

Offgas system isolation trip set at <2.1/5 Ci/see where 5 = average gamma energy from noble gas in e.

offgas after holdup line (Mev). Air ejector isolation valve closure time delay shall not exceed 15 minutes.

f.

Unless SRM chambers are fully inserted.

g.

Not applicable when IRM on lowest range.

h.

With one or more instrument channel (s) inoperable in one ADS trip system, place the relay contact (s) for the inoperable initiation signal in the tripped condition within 4 days, or declare ADS inoperable and take the action required by Specification 3.4.B.3.

With one or more instrument channel (s) inoperable in both ADS trip systems, restore ADS initiation capability in at least one trip system within I bour, or declare ADS inoperable and take the action required by Specification 3.4.B.3.

Relief valve controllers shall not be bypassed for any more than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> (total time for all controllers) in any 30-day period and only one relief valve controller may be bypassed at a time.

OYSTER CREEK 3.1-16 Amendment No.: 75,108,110,171,184,190

i TABLE 3.1.1 (CONTD) i.

.With two core spray systems OPERABLE:

1.

A maximum of two core spray booster pump differential pressure (d/p) switches j

may be inoperable provided that the switches are in opposing ADS trip systems

[i.e., only: either RV-40 A&D or RV-40 B&C). Place the relay contacts associated with the inoperable d/p switch (es)in the de-energized position, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Restore the inoperable d/p switch (es) within 8 days, or declare ADS inoperable l

and take the action required by Specification 3.4.B.3; 1

l or,

(

j 2.

If two inoperable d/p switches are in the same ADS trip system [i.e., RV-40 A&B or RV-40 C&D], place the relay contacts associated with the inoperable d/p switch (es) in the de-energized position, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the inoperable d/p switches within 4 days, or declare ADS inoperable and take the action required by Specification 3.4.B.3.

With only one core sorav system OPERABLE:

i If one or more d/p switches become inoperable in the OPERABLE core spray system, declare ADS inoperable and take the action required by Specification 3.4.B.3.

1 J.

Not required below 40% of rated reactor thermal power.

)

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(

l i

i OYSTER CREEK 3.1-16a Amendment No.:1/1,174,190 1

ThBLE 4.1.1 (cont'd)

- s instrument Channel Check Calibrate Int Remarks (Acolv to Test & Calibration)

29. Drywell High N/A Each re-Each re-I Radiation fueling fueling 4

outage outage i

30. Automatic Scram N/A N/A 1/wk Note 1 Contactors i

l

31. Core Spray Booster Pump l

Differential Pressure N/A 1/3 mo 1/3 mo By application of a test pressure i

i

• Calibrate prior to startup and normal shutdown and thereaRer check 1/s and test 1/wk until no longer required.

LEGEND: N/A = Not Applicable; l/s = Once per shift; 1/d = Once per day; 1/3d = Once per 3 days; 1/wk = Once per week; 1/mo = Once per month; 1/3 mo = Once every 3 months; l/20 mo = Once every 20 months; l/24 mo = Once every 24 months Note 1:

Each automatic scram contactor is required to be tested at least once per week. When not tested by other means, the weekly test can be performed by using the subchannel test switches.

, Note 2:

At least daily during reactor POWER OPERATION, the reactor neutron flux peaking factor shall be estimated and flow-referenced APRM scram and rod block settings shall be adjusted, if necessary, as specified in Section 2.3 Specifications A.1 and A.2.

Note 3:

Calibrate electronic bistable trips by injection of an external test current once per 3 months.

Calibrate transmitters by application of test pressure once per 12 months.

3 i

1 The following notes are only for item 15 of Table 41.1:

A channel may be taken out of service for the purpose of a check, calibration, test or maintenance without i

declaring the channel to be inoperable.

The Channel Test shall also demonstrate that control room alarm annunciation occurs if any of the a.

following conditions exists:

i

1) Instrument indicates measured levels above the alarm setpoint.

2) Instrument indicates a downscale failure.

3) Instrument controls not set in operate mode.

4) Instrument electrical power loss.

OYSTER CREEK 4.1-6 Ameridment No.: 63,80,108,116,141,152, 1//1;190 Changes 5, 7