ML20139A295

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Discusses Change to Bases for TS 3/4.1.2 Submitted on 961129.Change Increases Required Volume of 2,000 Ppm Borated Water in RWST from 58,965 Gallons to 100,000 Gallons.No Objection from NRC to Proposed Change
ML20139A295
Person / Time
Site: Beaver Valley
Issue date: 04/22/1997
From: Brinkman D
NRC (Affiliation Not Assigned)
To: Cross J
DUQUESNE LIGHT CO.
References
TAC-M97409, NUDOCS 9704250188
Download: ML20139A295 (4)


Text

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1 April 22, 1997 Mr. J. E. Cross President - Generation Group Duquesne Light Company i

Post Office Box 4 Shippingport. PA 15077

SUBJECT:

CHANGE TO BASES OF BEAVER VALLEY POWER STATION. UNIT NO. 2 TECHNICAL SPECIFICATION 3/4.1.2 (TAC NO. M97409) l

Dear Mr. Cross:

By letter dated October 10. 1996. Duquesne Light Company (DLC) provided the Beaver Valley Power Station. Unit No. 2 (BVPS-2) Cycle 7 reload design and Core Operating Limits Report (COLR).

That letter also provided notification that a change to the Bases for technical specification (TS) 3/4.1.2 would be required and would be forwarded by separate letter following verification of the ap3ropriate value..The required Bases change was provided by DLC letter i

dated govember 29, 1996. The change increases the required volume of 2000 ppm borated water in the refueling water storage tank (RWST) from 58.965 gallons to 100.000 gallons.

DLC stated that the increased volume (100.000 gallons) reflects the exoected upper bound for the amount of 2000 ppm borated water from the RWST that is required to satisfy the maximum cycle shutdown margin requirements at the beginning-of-cycle from full power 3eak xenon conditions.

We note that the new, increased volume remains bounded )y the requirement of TS 3.1.2.8 which requires a minimum volume of 859.248 gallons in the RWST.

Therefore, we have no objection to the proposed change.

A copy of revised Bases page B 3/4 1-3 is enclosed for your use.

Sincerely.

(original signed by)

Donald S. Brinkman. Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-412

Enclosure:

BVPS-2 TS Bases Page B 3/4 1-3 cc w/ encl:

See next page DISTRIBUTION:

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o April 22, 1997 Mr. J. E. Cross President - Generation Group Duquesne Light Company Post Office Box 4 Shippingport, PA 15077

SUBJECT:

CHANGE TO BASES OF BEAVER VALLEY POWER STATION, UNIT N0. 2 TECHNICAL SPECIFICATION 3/4.1.2 (TAC NO. M97409)-

\\

Dear Mr. Cross:

l By letter dated October 10. 1996. Duquesne Light Company (DLC) provided the

)

Beaver Valley Power Station, Unit No. 2 (BVPS-2) Cycle 7 reload design and Core Operating Limits Report (COLR). That letter also provided notification that a change to the Bases for technical specification (TS) 3/4.1.2 would be required and would be forwarded by seaarate letter following verification of the ap3ropriate value. The required 3ases change was provided by DLC letter dated lovember 29, 1996. The change increases the required volume of 2000. ppm borated water in the refueling water storage tank (RWST) from 58,965 gallons to 100.000 gallons.

DLC stated that the increased volume (100,000 gallons) reflects the ex>ected upper bound for the amount of 2000 ppm borated water from the RWST tlat is required to satisfy the maximum cycle shutdown margin requirements at the beginning-of-cycle from full power Jeak xenon condition.s.

We note that the new, increased volume remains bounded )y the requiremant of TS 3.1.2.8 which requires a minimum volume of 859.248 gallons in the RWST.

Therefore, we have no objection to the proposed change.

A copy of revised Bases page B 3/41-3 is enclosed for your use.

Sincerely.

Donald S. Brinkman, Senior Project Managar Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket No. 50-412

Enclosure:

BVPS-2 TS Bases Page B 3/4 1-3 cc w/ encl: See next page

y

4 J. E. Cross Beaver Valley Power Station Duquesne Light Company Units 1 & 2 cc

Jay E. Silberg, Esquire Bureau of Radiation Protection Shaw, Pittman. Potts & Trowbridge Pennsylvania Department of 2300 N Street NW.

Environmental Resources Washington, DC 20037 ATTN:

R. Barkanic Post Office Box 2063 R. K. Brosi, Manager Harrisburg, PA 17120 Nuclear Safety Department (BV-A) i Duquesne Light Company Beaver Valley Power Station Mayor of the Borrough of PO Box 4 Shippingport i

j Shippingport, PA 15077 Post Office Box 3 Shippingport, PA 15077 Commissioner Roy M. Smith West Virginia Department of Labor Regional Administrator, Region I Building 3. Room 319 U.S. Nuclear Regulatory Commission Capitol Complex 475 Allendale Road Charleston, WVA 25305 King of Prussia, PA 19406 John D. Borrows Resident Inspector i

4 Director. Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 298 180 East Broad Street Shippingport, PA 15077 Columbus, OH 43266-0573 Director Pennsylvania Emergency Duquesne Light Company l

Management Agency Beaver Valley Power Station Post Office Box 3321 P0 Box 4 Harrisburg PA 17105-3321 Shippingport, PA 15077 ATTN:

S. C. Jain, Vice President Ohio EPA-DERR Nuclear Services (BV-A)

ATTN: Zack A. Clayton Post Office Box 1049 Columbus, OH 43266-0149 i

Dr. Judith Johnsrud National Energy Committee Sierra Club 4

433 Orlando Avenue State College, PA 16803

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NPF-73 REACTIVITY CONTROL SYSTEMS l*

BASES i

3/4.1.2 BORATION SYSTEMS (Continued) i The OPERABILITY of the Refueling Water Storage Tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is j

available for injection by the ECCS in the event of either a LOCA or i

a steamline break.

The limits on RWST minimum volume and boron concentration ensure that:

1) sufficient water is available within containment to permit recirculation cooling flow to the core, 2) the reactor will remain subcritical in the cold condition (68 to 212 i

degrees-F) following a small break LOCA assuming complete mixing of the RWST, RCS and ECCS water' volumes with all control rods inserted e

i except the most reactive control rod assembly (ARI-1), 3) the reactor l

will remain suberitical in the cold condition following a large break 2

LOCA (break flow area > 3.0 ft ) assuming complete mixing of the RWST, RCS, ECCS, chemical addition tank, containment spray system piping, and other water volumes that may eventually reside in the sump Post-LOCA with all control rods assumed to be out (ARO), 4) long term subcriticality following a steamline break assuming ARI-1 and to i

preclude fuel failure.

i The maximum allowable value for the RWST boron concentration forms the basis for determining the time (post-LOCA) at which i

operator action is required to switch over the ECCS to. hot leg i

recirculation in order to avoid precipitation of the soluble boron.

I The limitations for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable l

below 3 50'F provides assurance that a

mass addition pressure j

j transient can be relieved by the operation of a

single PORV.

Substituting a Low Head Safety Injection pump for a charging pump in MODES 5 and 6 will not increase the probability of an overpressure i

event since the shutoff head of the Low Head Safety Injection pumps is below the setpoint of the overpressure protection system.

i The boration capability of either system is sufficient to provide a SHUTDOWN MARGIN from all operating conditions of 1.77%

Ak/k after xenon decay and cooldown to 200*F.

The maximum boration capability requirements occur at BOL from full power peak xenon conditions and requires 13,390 gallons of 7000 ppm borated water from the boric acid storage tanks or 100,000 gallons of 2000 ppm borated l

water from the refueling water storage tank.

With the RCS temperature below 350'F, one boron injection flow path-is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.

BEAVER VALLEY - UNIT 2 B 3/4 1-3 Revised by NRC letter dated April 22, 1997

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