ML20005F091

Amend 135 to License DPR-16,revising Tech Specs to Delete Tech Spec Safety Limit 2.1.E Which Required at Least Two Recirculation Loops to Be Fully Open Except When Reactor Vessel Head Off

ML20005F091
Person / Time
Site:	Oyster Creek
Issue date:	12/30/1989
From:	Stolz J Office of Nuclear Reactor Regulation
To:	GPU Nuclear Corp, Jersey Central Power & Light Co
Shared Package
ML20005F092	List: ML20005F091 ML20005F096
References
DPR-16-A-135 NUDOCS 9001120282
Download: ML20005F091 (9)

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-JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TD PROVISIONAL OPERATING LICENSE Amendment No.135 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), datec March 31, 1988 as as supplemented in letters dated November 15, 1988 and August 23, 1989 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 f acility 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 tne 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 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 Comission's regulations and all applicable requirements have been satisfied.

1 90011202B2 891230 DR. ADOCK 050 g 9

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, j

and paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby L

amended to read as follows:

(2) Technical Sptcifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.135, are hereby incorporated in the licente.. GPU Nuclear Corporation shall operate the facility in 5

accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.

THE NVCLEAR REGULATORY COMMIS$10N

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[oh F. Stolz, Director I

P ect Directorate I-4 Division of Reactor Projects - I/I!

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical

. Specifications Date of Issuance: Dacember 30, 1989

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m-i ATTACHMENT TO LICENSE AMENDMENT.NO.135 i

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i PROV1510NAL OPERATING,(ICENSE NO. DPR-16 i

DOCKETNO.50-[19 i

Replace the following pages of the Appendix A Technical Specifications with the enclosed.pages as indicated. The revised pages are identified by i

l amendment number and contain vertical lines indicating the areas of change.

i Elm 211 insert 2.1-1 2.1-1

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2.1-3 2.1-3 3.3-3 3.3-3 3.3-3a l

3.3-8 3.3-8 3.38a I

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SECTION 2 SAFETY tlMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMIT - FUEL CLADDING INTEGRITY Applicability: Applies to the interrelated variables associated with fuel themal behavior.

Objective:

To establish limits on the important thermal hydraulic variables to assure the integrity of the fuel cladding.

Specifications:

A.

When the reactor pressure is greater than or equal to 800 psia and the core flow is greater than or equal to 105 of rated, the existence of a minimum critical power ratio (MCPR) less than 1.07 i

shall constitute violation of the fuel cladding integrity safety limi t.

B.

When the reactor pressure is less than 800 psia or the core flow is less than 10% of rated, the core themel power shall not exceed 25%

of rated themal power.

C.

In the event that reactor parameters exceed the limiting safety system settings in specification 2.3 and a reactor scram is not initiated by the associated protective instrumentation, the reactor shall be brought to, and remain in, the cold shutdown condition until an analysis is perfomed to detemine whether the safety limit established in specification 2.1. A and 2.1.8 was exceeded.

D.

During all modes of reactor operation with irradiated fuel in the reactor vessel, the water level shall not be less than 4'8" above the top of active fuel.

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Bases:

The fuel-cladding integrity safety limit is set such that no fuel l

damage is calculated to occur if the limit is not violated.

Since the parameters which result in fuel damage are not directly observable during reactor operation the thenna1 and hydraulic conditions resulting in a departure from nucleate boiling have been used to mark the beginning of the region where fuel damage could occur.

Although it is recognized that a departure from nucleate boiling would not necessarily result in damage to BWR fuel rods, the critical power at which boiling transition is calculated to occur has been adopted as a convenient limit.

However, the uncertainties in monitoring the core operating state and in the procedure used to calculate the Oyster Creek 2.1 -1 Amendment No.: [135

cooling capability could lead to elevated cladding temperatures and clad perforation. With a water level above the top of the active fuel, adequate cooling is maintained and the decay heat can easily be accomodated.

It should be noted that during power generation there is no clearly defined water level inside the shroud and what actually exists is a mixture level.

This mixture begins within the active fuel region and extends up thmugh the moisture separators.

For the purpose of this specification water level is defined to include mixture level during power operations.

The lowest point at which the water level can presently be monitored is.4'8" above the top of active fuel.

Although the lowest reactor I

water level limit which ensures adequate core cooling is the top of the active fuel, the safety limit has been conservatively established at 4'8" above the top of active fuel.

REFERENCES (1)

NE00-24195, General Electric Reload Fuel Application for Oyster Creek.

Oyster Creek 2.1 -3 Amendment No.: Jd 135

i E.

Reactor Coolant Quality I

1.

The reactor coolant (uality during power operation with steaming rates i

to the turbine-condenser of less than 100,000 pounds per hour shall be i

limited to:

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

I chloride ion 0.1 ppm 2.

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

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

3.

The reactor coolant quality during power operation with steaming rates to the turbine-condenser of greater than or equal to 100,000 pounds per hour shall be limited to:

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

chloride ion 0.5 ppm 4

When the maximum conductivity or chloride concentration limits given in 3.3.E.3 are exceeded, an orderly shutdown shall be initiated innediately, and the reactor coolant temperature shall be reduced to less than 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5.

During power operation with steaming rates on the turbine-condenser of greater than or equal to 100,000 pounds per hour, the time limit above 1.0 uS/cm at 25'C (77'F) and 0.2 ppm chloride shall not exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for any single incident.

6.

When the time limits for 3.3.E.5 are exceeded, an orderly shutdown shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

L F.

Recirculation Loop Operability L

1.

During POWER OPERATION, all five recirculation loops shall be p

OPERATING except as specified in Speciftcation 3.3.F.2.

2.

POWER OPERATION with one idle recirculation loop is permitted provided that the idle loop is not isolated from the reactor vessel.

3.

If Specifications 3.3.F.1 and 3.3.F.2 are not met, an orderly shutdown shall be initiated innedtately until all operable control rods are fully inserted and the reactor is in either the REFUEL MODE or SHUTDOWN CONDITION within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4.

With reactor coolant temperature greater than 212*F and irradiated fuel in the reactor vessel, at least one recirculation loop discharge valve and its associated suction valve shall be in the full open i

position.

5.

If Specification 3.3.F.4 is not met, innediately open one recirculation loop discharge valve and its associated suction valve.

' OYSTER CREEK 3.3-3 Amenenent No.: N 135

n 6.

With reactor coolant temperature less than 212'F and irradtated fuel in the reactor vessel.at least one rectreulation loop discharge valve and its associated suction valve shall be in the full open position unless the reactor vessel ts flooded to a level above 185 inches TAF or unless the stear separator and dryer are removed.

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OYSTER CREEK 3.3-3a Amendment No. 135 l

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i pH, chlorice, and other chemical parameters are made to determine the cause of the unusual Conductivity and instigate proper corrective action. These can be done before limiting conditions, with respect to variables affecting the boundaries of the reactor 4 r coolant. are exceeded.

Several technioues are available to correct off-standard reactor water cuality conditions including removal of impurities from reactor water by the cleanup system, reducing input I

of impurities causing off-standard conditions by reducing power and reducing the reactor coolant temperature to less than 212'F.

The major benefit of reducing the reactor coolant temperature to less than 212'F is to reduce the temperature depenaent corrosion rates and thereby provide time for the cleanup system to re-establish 1

proper water cuality.

Specifications 3.3.F.I and 3.3.F.2 recuire a minimum of four OPERATING recirculation loops during reactor POWER OPERATION.

Core parameters have not been established for POWER OPERATION with less

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than four OPERATING loops.

Therefore, Specification 3.3.F.3 reautres reactor POWER OPERATION to be terminated and the reactor placed in the REFUEL MODE or SHUTDOWN CONDITION within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

During four loop P0 DER OPERATION the idle loop is reautred to have its discharge valve closed and its discharge bypass and suctio')

valves open.

This minimizes the occurrence of a severe cold water addition transient curing startup of an idle loop.

In addition, with the discharge bypass and suction valves in an idle loop open the coolant inventory in the loop 1s available during LOCA blowcown.'

l Specifications 3.3 F.4"and 3.3.F.6 assure that an adeounte flow path exists from the annular space, between the pressure vessel wall and the core shroud, to the core region.

This provides sufficient hydraulic communication between these areas, thus L

assuring that reactor water level instrument readings are indicative of the water levt1)in the core region.

For the counding loss of feedwater transienti2, a single fully open recirculation loop transfers coolant from the, annulus to the core region at approximate f

circulationb.ivetimesthehoiloffratewithnoforced With the reactor vessel flooded to a level above 185 inches TAF or when the steam separator and dryer are removed, the core region is in hydraulic comunication with the annulus above the core region and all recirculation loops can therefore be isolated. When the steam separator and dryer are removed, safety L

limit 2.1.D ensures water level is maintained above the core shroud.

References (1)

FDSAR, Volume I, Section IV-2 (2) letter to NRC dated May 19, 1979, " Transient of May 2, 1979" l

(3)

General Electric Co. Letter G-EN-9-55, " Revised Natural Circulation Flow Calculation", dated May 29, 1979 I4)

L1 censing Application Amendment 16, Design Requirements Section (5)

(Deleted)

(6)

FDSAR, Volume I, Section IV-2.3.3 and Volume II Appendix H (7)

FDSAR, Volume I, Table IV-2-1 (8)

Licensing Application Amendment 34, Question 14 OYSTER CREEK 3.3-8 Amendment No.: f h 135

r (9) Licensing Application Amenoment 28. Item !!!-8 2 (10) Licensing Application Amenoment 32 Question 15 (11) (Deletec)

(12) (Deletec)

(13) Licensing Application Amenenent 16. Page 1 (14) GPUN TDR 725 Rev. 0: Testing and Evaluation of Irraciated Reactor vessel Materials Surveillance Program Specimens.

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l 0YSTER CREEK 3,3 8a Amendment No. 135 l

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