ML20207Q120

Amend 95 to License DPR-30,reflecting Cycle 9 Reload Fuel & Transient Analyses,Removing Provisions for Single Loop Operation as License Condition & Incorporating Similar Provisions Into Tech Specs

ML20207Q120
Person / Time
Site:	Quad Cities
Issue date:	01/16/1987
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207Q121	List: ML20207Q120 ML20207Q124 ML20207Q125
References
NUDOCS 8701230065
Download: ML20207Q120 (20)

Text

.

UNITED STATES 6

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NUCLEAR REGULATORY COMMISSION a

WASHINGTON, D. C. 20555

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COMMONWEALTH EDISON COMPANY AND IOWA-II.LINOIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 OVAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-30 1.

The Nuclear Regulatory Commission (the Comissioni has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated September 18, 1986, as clarified December 10 and 23, 1986, complies with the standards and recuirements 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 Comission; C.

There is reasonable assurance (1) that the activities authorized 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 reouirements have been satisfied.

2.

Accordingly, the license is amended by deleting license condition paragraph 3.J and by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. and 3.J of Facility Operating License No. DPR-30 are hereby amended to read as follows:

8701230065 870116 PDR ADOCK 05000265 P

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2 B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

J.

Deleted.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 7

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John

. Zwolinski, Director RWR Project Directorate #1 Division of BWR Licensing

Attachment:

Changes to License No. DPR-30 and the Technical Specifications Date of Issuance:

January 16, 1987

ATTACHMENT TO LICENSE AMENDMENT N0. 95 FACILITY OPERATING LICENSE NO. OPR-30 DOCKET NO. 50-265 1.

For your convenience we are enclosing a revised copy of page 7 of DPR-30 for Quad Cities Nuclear Power Station, Unit 2.

The text on page 7a of the license has been relocated to page 7.

2.

Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 11 11 1.0-5 1.0-5 Figure ?.1-1 Figure 2.1-1 Figure 2.1-3 Figure 2.1-3 3.5/4.5-10 3.5/4.5-10 Figure 3.5-1 (Sheets 1-6)

Figure 3.5-1 (Sheets 1-6) 3.6/4.6-5 3.6/4.6-5 3.6/4.6-Sa 3.6/4.6-Sa 3.6/4.6-5b 3.6/4.6-13 3.6/4.6-13 3.6/4.6-13a l

7-3.J Deleted 3.K Post-Accident Sampling [7/31/86 correction to Amd. 901 A program will be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant chimney effluents, (Amd. 90 and containment atmosphere samples under accident conditions.

6/10/86i The program shall include the following:

1.

Training of personnel, 9

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis eauipment.

4.

This license is effective as of the date of issuance, and shall expire at midnight, February 15, 2007.

FOR THE ATOMIC ENERGY COMMISSION Original license signed by:

A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing

Enclosures:

Appendices A and B -- Technical Specifications Date of 1ssuance:

December 14, 1972 Amendment No. 95

+

]

e QUAD CITIES DPR-30 TABLE OF CONTENTS (Cont'd)-

Page

'3.5/4.5 CORE CONTAINMENT COOLING SYSTEMS 3.5/4.5-1 l

A. -Core Spray Subsystems and the LPCI Mode of the RHR System 3.5/4.5-1 B.

Containment Cool.ing Mode of the RHR System 3.5/4.5-3 C.

HPCI Subsystem 3.5/4.5 4 D.

Automatic Pressure Relief Subsystems 3.5/4.5-5 E.

Reactor Core Isolation Cooling System 3.5/4.5-6 F.

Minimum Core and Containment Cooling System Availability 3.5/4.5-6 G.

Maintenance of Filled Discharge Pipe 3.5/4.5-7 H.. Condensate Pump Room Flood Protection 3.5/4.5-8 I.

Average Planar Linear Heat Generation Rate (APLHGR) 3.5/4.5-9 J.

Local LHGR 3.5/4.5-9 K.

Minimum Critical Power Ratio (MCPR) 3.5/4.5-10

'3.5 Limiting. Conditions for Operation Bases 3.5/4.5-11 4.5 Survelliance Requirements Bases' 3.5/4.5-16 3.6/4.6 PRIMARY SYSTEM BOUNDARY 3.6/4.6-1 A.

Thermal Limitations 3.6/4.6-1 8.

Pressurization Temperature 3.6/4.6-1 C.

Coolant Chemistry 3.6/4.6-2 0.

Coolant Leakage 3.6/4.6-3 E.

Safety and Relief Valves 3.6/4.6-4 F.

Structural Integrity 3.6/4.6-4 3.6/4.6-5 G.

Jet Pumps H.

Recirculation Pump Flow limitations 3.6/4.6-5

[

I.

Shock Suppressors (Snubbers) 3.6/4.6-5a 3.6 Limiting Conditions for Operatong Bases 3.6/4.6-8 3.7/4.7 CONTAINMENT SYSTEMS 3.7/4.7-1 A.

Primary Containment 3.7/4.7-1 3.7/4.7-7 B.

Standby Gas Treatment System

~

3.7/4.7-8 C.

Secondary Containment D. ' Primary Containment Isolation Valves 3.7/4.7-9 3.7/4.7-11 3.7 Limiting Conditions for Operation Bases 3.7/4.7-15 4.7 Surveillance Requirements Bases 3.8/4.8-1 3.8/4.8 RADI0 ACTIVE EFFLUENTS 3.8/4.8-1 Gaseous Effluents 3.8/4.8-6a B.

Liquid Effluents 3.8/4.8-9 C.

Mechanical Vacuum Pump 3.8/4.8-10 D.

Environmental Monitoring Program 3.8/4.8-13 E.

Solid Radioactive Waste F.

Miscellaneous Radioactive Materials Sources 3.8/4.8-14 3.8/4.8-14a H.

Control Room Emergency Filtration System 3.8/4.8.A Limiting Conditions for Operation and Survelliance Req. Bases 3.8/4.8 15 11 Amendment No. $/. $9, 95

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QUAD CITIES OPR-30 II. Dose Equivalent I-131 - That^ concentration of I-131 (microcurie /

gram) wnicn alone would produce the same thyrold dose as the quantity and isotopic mixture of I-131, I-132. I-133, I-134, and I 135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, " Calculation of Distance Factors For Power and Test Reactor Sites."

l JJ. Process Control Program (PCP$ - Contains the sampling, analysis, and formulation determination by 1 ditch solidification of radioactive wastes from liquid systems is assured.

KK. Offsite Dose Calculation Manual (00CM) - Contains the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, and in the calculation of gaseous and liquid effluent monitor alarm / trip setpoints.

LL. Channel Functional Test (Radiation Monitor) - Shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/ or trio functions.

MM.

Source Check - The qualitative assessment of instrument response when the sensor is exposed to a radioactive source.

NN. Member (s) of the Public - Shall include all persons who are not occupationally associated with tne plant.

This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occuoational, or other purposes not associated with the plant.

00. Dual Loop Operation (DLO) - Reactor power operation with both recirculation pumps running.

PP.

Single Loop Operation (SLO) - Reactor pcwer operation with one recirculation pump running.

1.0-5 Amendment No. g5, 95

DPR--30 MRMFlowReferencescram and @RM Rod Block Settings 138 128-lil-Ill-e 90-

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DPR-30 140

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• NATURAL CIRCULATION LINE NOMINAL, CONSTANT XENON 60 _

100/100 POWER / FLOW LINE 40 _

g Operating Region Suppe ed By N.E.D.O. - 24167 r N.E.D.O. 22192 20% PUMP

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SPEED LINE Natural Circulat' s

Limited per Tec.a.

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3.6.H.3 and 2.1.A.4.

l RATED CONDITIONS POWER 2511 MWth CORE '/ LOW 98 M1bs/HR 4

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20 40 60 80 100 120 j

W CORE FLOW RATE (% OF RATED)

T FIGURE 2.1-3 (SCHEMATIC)

Amendment No. 64 APRM FLOW BIAS SCRAM RELATIONSHIP 95 TO NORMAL OPERATING CONDITIONS

j QUAD-CITIES OPR-30 j

within the prescribed limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition within 36' hours. Surveillance and corresponding action shall continue untti reactor operation is within the prescribed limits. Maximum allowable LHGR for all 8X8 fuel types is 13.4 KW/ft.

K.

Minimum Critical Power Ratio (MCPR)

K.

Minimum Critical Power Ratio (MCPR)

During steady-state operation at The MCPR shall be determined daily during rated core flow, MCPR shall be steady-state power operation above 257. of greater than or equal to:

rated thermal power.

l 1.38 for Tave 1 0.73 secs I

I 1.43 for tave 2. 0.86 secs

.0.385 tave + 1.099 f

for 0.73 < Tave < 0.86 secs where tgyg =

mean 20'4 scram insertion time for all surveillance data from specification t!.3.C which has been generated in the current cycle.

For core flows other than rated, these nominal values of MCPR shall be increased by a factor of kf where kr is as shown in Figure 3.5.2.

If any time during operation it is de-termined by normal surveillance that the 1imitIng value for MCPR 1s being exceeded, action shall be initiated within 15 minutes to restore opera-tion to within the prescribed limits. If the steady-state MCPR is not returned to within the prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surve11-lance and corresponding action shall continue until reactor operation is within the prescribed limits.

3.5/4.5-10 Amendment No. $7.97,'/7,F/.%', 95

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---,;7--------;------

l CUAD-CITIES DPR-30 G.

Jet Pumps G.

Jet Pumps 1.

Whenever the reactor is in the 1.

Whenever there is recircu-Startup/ Hot Standby or Run lation flow with the reactor in modes, all jet pumps shall be the Startup/ Hot Standby or Run intact, and all operating jet modes, jet pump integrity and Dumps shall be operable.

If it operability shall be checked is determined that a jet pump is daily by verifying that the Inoperable, an orderly shutdown following two conditions do not shall be initiated and the occur simultaneously:

reactor shall be in a cold shutdown condition within 24 a.

The recirculation aumo flow hours.

differs by more than 101 from the establisned 2.

Flow indication frc each of the speed-flow characteristics.

20 jet pumps shall be verified prior to initiation of reactor b.

The indicated total core startup from a cold shutdown flow is more than 10%

condition.

greater than the core flow value derived from esta0-3.

The indicated core flow is the lished core plate DP-core sum of the flow indication from flow relationships.

each of the 20 jet pumps.

If flow indication failure occurs 2.

Additionally, when operating for two or more jet pumps, with one recirculation pump with immediate corrective action the equalizer valves closed, the shall be taken.

If flow diffuser to lower plenum indication for all but one jet differential pressure shall be pump cannot be obtained within checked daily, and the dif-12 hours, an orderly shutdown ferential pressure of any jet shall be initiated and the pump in the idle loop shall not reactor shall be in a cold vary by more than 10% from shutdcwn condition within 24 established patterns.

hours.

3.

The baseline data required to H.

Recirculation Pump Flow Limitations l

evaluate the conoitions in Specifications 4.6.G.1 and 1.

Whenever both recirculation 4.6.G.2 will be acquired each pumps are in operation, pump operating cycle.

speeds shall be maintained within 10% of each other when H.

Recirculation Pump Flow Limitations l

power level is greater than 80%

and within 15% of each other Recirculation pumps speed shall be when power level is less than checked daily for mismatch.

80%.

2.

If Specification 3.6 H.1 cannot be met, one recirculation pump shall be tripped.

3.6/4.6-5 Amendment No. )<, 95 I

QUAD-CITIES DPR-30 3.

Prior to Sinale Loop Operation for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the following restrictions are required:

a.

The MCPR Safety Limit shall be increased by 0.01. (T.S.

1.lA);

b.

The MCPR Operating Limit shall be increased by 0.01.

(T.S. 3.5.K):

c.

The MAPLHGR Operating Limit shall be reduced by a multiplicative factor of 0.84.

(T.S. 3.5.I);

d.

The flow biased APRM Scram and Rod Block Setpoints shall be reduced by 3.5% to read as follows:

T.S. 2.1.A.1; 5 1 58HD + 58.5 T.S. 2.1.A.1;

• S 1 (.58HD + 58.5) FRP/MFLPD T.S. 2.1.B; S 1 58HD + 46.5 T.S. 2.1.B;*

S 1 (.58HD + 46.5) FRP/MFLPD T.S. 3.2.C (Table 3 2-3);*

APRM upscale 1 (.58HD +

46.5) FRP/MFLPD In the event that MFLPD exceeds FRP.

e.

The flow biased RBM Rod Block setpoints shall be reduced by 4.0% to read as follows:

T.S. 3.2.C (Table 3.2-3);

RBM Upscale i.65WD + 38 f.

The suction valve in the idle loop shall be closed and electrically isolated except when the idle loop is being prepared for return to service.

3.6/4.6-Sa Amendment No. af, 95

QUAD-CITIES DPR-30 I

I.

Shock Suppressors (Snubbers)

I.

Shock Suppressors (Snubbers) 1.

During all modes of operation' The following surveillance except Shutdown and Refuel, all.

requirements apply to all snubbers snubbers listed in Table 3.6-1 listed in Table 3.6-1.

shall be operable except as noted in 3.6.1.2 following.

1.

Visual inspections shall be performed in accordance with the 2.

From and after the time that a following schedule utilizing the snubber is determined to be acceptance criteria given by inoperable, continued reactor Specification 4.6.1.2.

operation is permissible during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> only if Number of Snubbers the snubber is sooner made Found Inoperable Next operable.

During Inspection Required or During Inspec-Inspection 3.

If the requirements of 3.6.1.1 tion Interval Interval and 3.6.1.2 cannot be met, and orderly shutdown shall be 0

18 months initiated and the reactor shall

25%

be in a cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

I 12 months

25%

4.

If a snubber is determined to be inoperable while the reacter is 2

6 months in the Shutdwon or Refuel mode, t 25%

the snubber shall be made operable prior to reactor 3, 4 124 days start-up.

t 25%

5.

Snubbers may be added to 5,6,7 62 days safety-related systems without t 25%

prior license Amendment to Table 3.6-1 provided that a revision

>8 31 days to Table 3.6-1 is included with

~+ 25%

the next license amendment i

request.

The required inspection interval shall not be lengthened more than one step at a time.

Snubbers may be categorized in two groups, ' accessible' or

' inaccessible' based on their accessibility for inspection during reactor operation. These two groups may be inspected independently according to the above schedule.

3.6/4.6-Sb Amendment No. //, $J,70, 95

4 QUAD-CITIES DPR-30 G. Jet Pumps failure of a jet pump nozzle assembly holddown mechanism, nozzle assembly, and/or riser increases the cross-sectional flow area for blowdown following the postulated design-basis double-ended recirculation line break.

Therefore, if a failure occurs, repairs must be made to assure the validity of the calculated consequences.

The following factors form the basis for the surveillance requirements:

1.

A break in a jet pump decreases the flow resistance characteristic of the external piping loop causing the recirculation pump to operate at a higher flow condition when compared to previous operation.

2.

The change in flow rate of the failed jet pump produces a change in the indicated flow rate of that pump relative to the other pumps in that 1000 Comparison of the data with a normal relationship or pattern provides the indication necessary to detect a failed jet pump.

3.

The jet pump flow deviation pattern derived from the diffuser to lower plenum differential pressure readings will be used to further evaluate jet pump operability in the event that the jet pumps fall the tests in Sections 4.6.G.I and 2.

Agreement of indicated core flow with established power-core flow relationships provides the most assurance that recirculation flow is not bypassing the core through inactive or broken jet pumps.

This bypass flow is reverse with respect to normal jet flow. The indicated total core flow is a summation of the flow indications for the 20 individual jet pumps. The total core flow measuring instrumentation sums reverse jet pump flow as though it were forward flow. Thus, the indicated flow is higher than actual core flow by at least twice the normal flow through any backflowing pump. Reactivity inventory is known to a high degree of confidence so that even if a jet pu.rp failure occurred during a shutdown period, subsequent power ascension would promptly demonstrate abnormal control rod withdrawal for any power-flow operating map point.

A nozzle-riser system failure could also generate the coincident failure of a jet pump body; however, the converse is not true._ The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle riser system

failure, i

H. Recirculation Pump Flow limitation l

l The LPCI loop selection logic is described in the SAR, Section 6.2.4.2.5.

For some limited low probability accidents with the recirculation loop operating with large speed differences, it is possible for the logic to select the wrong loop for injection. For these limited conditions, the core spray itself is adequate to prevent fuel temperatures from exceeding allowable limits. However, to limit the probability even further, a procedural limitation has been placed on the allowable variation in speed between the recirculation pumps.

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3.6/4.6-13 Amendment No. Pf, 95 r

QUAD-CITIES OPR-30 The licensee's analyses indicate that above 80% power the loop select logic could not be expected to function at a speed differential of 15%. Below 80% power, the loop select logic would not be expected to function at a speed differential of 20%.

This specification provides a margin of 5% in pump speed differential.before a problem could arise. If the reactor is operating on one pump, the loop select logic trips that pump before making the loop selection.

Analyses have been performed which support indefinite single loop operation provic'ed i

the appropriate restriction are implemented within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The MCPR Safety Limit has been increased by 0.01 to account for core flow and TIP reading uncertainties which are used in the statistical analysis of the safety limit.

The MCPR Operating Limit has also been increased by 0.01 to maintain the same margin to the safety limit as during Dual Loop operation.

The flow biased scram and rod block setpoints are reduced to account for uncertainties associated with backflow through the idle jet pumps when the operating recirculation pump is above 20 - 40% of rated speed. This assures that the flow biased trips and blocks occur at conservative neutron flux levels for a given core flow.

The multiplicative 0.84 reduction of the MAPLHGR Operating Limit accounts for more rapid loss of core flow during some LOCA events wnen operating in Single Loop than during Oual Loop. The closure of the suction valve in the idle loop prevents the loss of LPCI flow through the idle recirculation pump into the downcomer.

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l 3.6/4.6-13a Amendment No. //, c5 1