ML20246M063

Amend 20 to License NPF-73,raising Max Allowed Svc Water Temp from 86 F to 89 F

ML20246M063
Person / Time
Site:	Beaver Valley
Issue date:	08/30/1989
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Cleveland Electric Illuminating Co, Duquesne Light Co, Ohio Edison Co, Toledo Edison Co
Shared Package
ML20246M069	List: ML20246M063 ML20246M071
References
NPF-73-A-020 NUDOCS 8909070085
Download: ML20246M063 (10)

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I f,c g-NUCLEAR REGULATORY COMMISSION 4

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WASHINGTON, D. C. 20555

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DUQUESNE LIGHT COMPANY

~0HIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO'EDI$0N COMPANY-DOCKET NO. 50-412 BEAVER VALLEY POWER STATION, UNIT NO. 2 MENDMENTTOFACILITYOPERATINGLICENSE Amendmeni No. 20 License No. NPF-73 1.

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

A.

The application for amendment by Duquesne Light Company, et al.

(the licenses) dated June 22, 1989, complies with the standcrds requirements of the Atomic Energy Act of 1954, asi 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 (i) that the activities authorized by this amer.dment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commi:;sion'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, t

89090700 yh12 PDR ADO PDC P

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licenst amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows:

(2) Technical Specifications The Techni:al Specifications contained in Appendix A, as revised through Amendment No. 20 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective on issuance.

FOR THE NUCLEAR REGULATORY COMMISSION v

J n F. Stolz, Dire r

P oject Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Reguletion r

Attachment:

Changes to the Technical Specifications Date of Isseance: August 30, 1989 l

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ATTACHMENT TO LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE NO. NPF-73 l

DOCKET NO.60-334 Replace the following pages of the Appendix A (Technical Specifications) with the enclosed pages as indicated.- The revised pages are identified by I

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

Remove Insert 3/4 6-6 3/4 6-6 3/4 6-7 3/4 6-7 3/4 6-0 3/4 6-c 3/4 6-13 3/4 6-13 3/4 7-13 3/4 7-13 B3/4 6-1 B3/4 6-1 B3/4 6-2 B3/4 6-2 1

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' CONTAINMENT SYSTEMS

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INTERNAL' PRESSURE-ll lLIMITING CONDITION FOR OPERATION i

L 3.6.1.4 Primary Containment internal air partial pressure shall be maintained

> 9.0 psia and within the acceptable operation range (below and to the'left of n

the applicable containment temperature limit line) shown on-Figure 3.6-1 as a

'l l-L function of service water temperature.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With 'the contain'nent _ internal air partial pressure < 9.0 psia or abnve the -

applicable containment temperature limit ~line shown on Figure.3.6-1, restore

,l the internal pressure to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.or be in at least HOT STANDBY within.the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and.in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS -4.6.1.4 The primary containment internal pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l BEAVER VALLEY - UNIT 2 3/4 6-6 Amendment No. 20

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1 NOTE 3:

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1. RWST TEMPERATURE BETWEEN 1

450f AND 500F, 10.5

2. MAxlWUM ALLOWABLE CONTAINMENT TEMPERATURE 1050F, 10.4

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3. M:Niuuu (LLowAB'.E CONTAINMENT AIR PARTIAL PREESURE 9.0 PSK.

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4. MAXsMUM SEMF WATER TMERATurst E90F q

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10.1 E

TEMPERATURE 8 60F

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$ f 9.9 Wh UNLCCEP"ABLE 98 e*aa OPERATICN fp ACCEPTABLE ap 9.7 yg CPERATiold 9.6 a

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9.3 CDNTAl.NMENT TEMPERATURE 21000F

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?I S.O s e 30 36 40 4 f.

60 66 60 66 70 76 40 46 8 !90 l 89 SERVICE WATER TEMPERA 10RE (DF) g7 i

FIGURE 3.6 1 MAXIMUM ALLOWABLE PRIMARY CONTAINMENT AIR PRES $URE VER$US SERVICE WATER TEMPERATURE 1

BEAVER VALLEY - Unit 2 3/4 6-7 Amendment No. 20

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CONTAINMENT SYSTEMS 7

AIR TEMPERATURE LIMITING CONDITION FOR OPERATION

3. 6.1. 5 Primary containment average air temperature shall be maintained:

Greater than or equal to BS*F and less than or equal to 105'F a.

of b.

Greater than or equal to 100 F and less than or equal to 105*F in accordance with the requirements of Figure 3.6-1.

APPLICABILITY:

MODES 1, 2, 3 and 4.

ACTION:

With tne containment average air temperature > 105"F or less than the minimum containment temperature prescribed in Figure 3.6-1 (85 F or 100 F) restore the average. air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT ST.'.NDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE001REMENTS 4,6.1. 5 The primary containment average maximum and minimum air temperatures shall be the arithmetical average of the temperatures at the following locations and shall be determined at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The nearest alternate detector may be used for temperature determination up to a maximum of one per location.

Location a.

Reactor Head Storage Area - Elev. 802'-0" 4

b.

Pressurizer Cubicle - Elev. 802'0"

c. -RC Anralus - Elev. 777'-4" d.

RHR Heat Exchanger - Elev. 801'-6" l

e.

RC Annulus - Elev. 701'-6" BEAVER VALLEY - UNIT 2 3/4 6-8 Amendment No. 20 q

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GNT31 MENT SYSTEMS-

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-30 WEILLANCE REQUIREMENTS TContig g i 4

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LVerifying that each automatic valve in the flow path actuates to.its; correct position on a test sigr,al.*

3.

. Initiating flew ibrough esch 5ervite Water subsystem and its'two.

associated recirculation. spray h a t exchangery, and verifying a flow rate of at least 11,000.gpm.

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At least.onge pg 5 years by performing at eir c) moko flow test through each spray header and verifying each spray nozzia is unobstructed.

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• The specified 18-coni.h surveillance interval datt.g the first fuel cycle may be extended to coincide with comp 1 61on of the first refueling outage.

BEAVER ViLLEY - (! NIT 2 3/4 6-13 Amendment No. M,20 me ___

x PLANT SYSTEMS 3/4.7.5 bH INATE HEAT SINK - OHIO RIVER 1

1~~JQIMGCONDITIONFO*fOPERATION 3.7.5.1 The ultimate heat sink shal's be OPERABLE with:

A ? inimum wate.r. Tevel at or above' elevation 654 Mean Sea Level., at' a.

the intake structure, and b.

An avf rage wathe temperature of < 89 F.

l APPLICABILITY: MODES 1,-2, 3 and 4.

ACTION:

With the requirements of the above specification not satisfied, be in at least HOT STANDBY within'6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.5.1 -The ultimate heat sink shall be determined OPERABLE at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the average water temperature and water level to be within their limits.

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u I/4.6 CONTAINMENT. SYSTEMS-BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensurei; that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths.and associated leak rates assumed in the accident analyses.

.This restriction, in conjunction with the leakage rate limitation, will limit the'-

site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure, P,.

As an added conservatism, the measured overall integrated leakage rate is further limited to < 0.75 La during performance of the periodic test to account for possiblelegradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consisteni, with the requirements of Appendix "J" of 10 CFR 50.

3/4.6.1.3 CONTAINMENT AIR LOCKS The' limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate.

Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage-during the intervals between air lock leakage tests.

3/4.6.1.4 and 3/4.6.1.5 INTERNAL PRESSURE AND AIR TEMPERATURE The limitations on containment internal pressure and average air temperature as a function of service water temperature ensure that 1) the containment

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structure is prevented from exceeding its design negative pressure of 8.0 psia, J

2) the containment peak pressure does not exceed the design pressure of 45 psig during LOCA conditions, and 3) the containment pressure is returned to sub-atmospheric conditions following a LOCA.

The containment internal pressure and temperature limits shown as a function of service water temperature describe the operational envelope l

that will 1) limit the containment peak pressure to less than its design value BEAVER VALLEY - UNIT 2 B 3/4 6-1 Amendment No. 20

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3/4.6.1.4 AND 3/4.6.1.5 INVERNAL PRESSURE AND AIR TEMPERATURE cf 45 psig and 2) ensure the containment internal pressure returns subatmospherir within 60 minutes following a LOCA. Additiokial operating marg #n is provided if-the containmetrt average air temperature is maintained.

above 100 F as'shovn on-Figure 3 6-1.

1 The limits on the parameters 6f Figure 3.6-1 are consistent with the assumptions of the accident snalyses.

3/4.6.1,6 CONTAINMENT S1RUCE RAL INTEGRITY This limitation ensures that the structural integrity of the containment vessel will t,e maintained comparable to ths original design st3ndards for the li fe of the facilit.y.

Structural integrity is required to ensure that the vessel will withstand The maximum pressure of 44.7 psig in the event of a_

LOCA.

The visual and Type A leakage tests are sufficient to demonstrate this j

capability.

3/4.6.2 DEPRESSUR12ATION AND. COOLING SYSTEMS 3/4._6.2.1 and 3/4._6.2.2 CONTAINV NT QUENCH AND RECIRCULATION SPRAY SYSTE The OPERABILITY of the containment spray systems ensures that containment depressurization and subsequent r& torn to subatmospheric pressure will occur in the ennt of 3 LOCA.

The pressure reduction and resultant termination of i

containment leakage are consistent with f.he assumptions used in the accident analyses.

3/4.6.2.3 CHEMICAL ADDIT}0N SYSTEM The OPERABILITY of the chemical addition system ensures that sufficient NaOH is added to the cor.tainment spray in the event of a LOCA.

The limits on NaOH winimum volume and concentration, ensure that 1) the 10 dine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corfosion effsets on components within contcinme4. are eini,mized.

These assumptions are consistent with the iodine removal efficiency escumeo in the accident analyses.

3/4.6.3 CONTAINMENT ISOLATION VALVES i

The OPERABILITY of the rentainment isolation valves onsuru that the con-L tainment atmosphere will be isulated frahi the outside environment in the event i

of a t-elease of radioactive material to the containment atmosphere or pressuri-2ation of the containment.

Containment isolation within the time limits speci-fied enseres that the release of radioactive meterial to thi environment will be consistent with the assumptions used in the anslyses for both a LOCA and majpr secondcry systen breaks.

BEAVER VALLEY - UN3T 2 B 3/4 6-2 Amendment No. 20 1

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