Text

Amend 39 to License NPF-43,revising Tech Specs & Bases to Clarify Tech Specs for Operation W/Moisture Separator Reheater Out of Svc
	ML20247D663
Person / Time
Site:	Fermi
Issue date:	09/01/1989
From:	Thoma J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20247D669	List: ML20247D663; ML20247D671; ML20247D685;
References
	NUDOCS 8909150038
	Download: ML20247D663 (18)
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-4 UNITED STATES,

g NUCLEAR REGULATORY COMMISSION i

E-WASHINGTON, D. C. 20555

... \\,p DETROIT EDISON COMPANY 4

WOLVERINE POWER SUPPLY COOPERATIVE, I.' INCORPORATED DOCKET NO. 50-341 l

FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.~39 l

License No. NPF-43 1.

The ~ Nuclear Regulatory Comission-(the Comission) has found that:

A.

The application for amendment by the Detroit' Edison Company.(the licensee)datedJanuary 27, 1988 as supplemented May 10, 1989, complies with the standards and requirements of the Atomic Enargy Act of 1954, 'as amended (the Act), and the Comission'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; J

l C.

There is reasonable assurance (1) that the activities authorized by

-I this amendment can be conducted without endangering the health and safety of the public,.and (ii) that such activities will be conducted 1

in compliance with the Comission's regulations; I

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 j

E.

The issuance of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifica-

.tions as indicated in the attachment to this license amendment and paragraph

.2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to j

read as follows:

Technical Specifications and Environmental Frutection Plan The Technical Specifications contained in Appendix A, as revisea through l

Amendment No. 39, and the Environmental Protection Plan contained in i

Appendix B, are hereby incorporated in the license. Deco shall operate

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the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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

FOR THE NUCLEAR REGULATORY COMMISSION John 0. Thoma, Acting Director Project Directorate'III-1

- t-Division of Reactor Projects - III,-

~IV, V & Special Projects Office of Nuclear Reactor Regulation-

Attachment:

Changes to the. Technical Specifications.

Date of Issuance:' September 1, 1989 I

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v ATTACHMENT TO LICENSE AMENDMENT NO. 39 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the' Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

- REMOVE INSERT viii viii

- xv xv 3/4 2-6 3/4 2-6 3/4 2-8 3/4 2-8 3/4 7-40 3/4 7-40 B 3/4 2-4 B 3/4'2-4 B 3/4 2-4a B 3/4 2-4b

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i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

.SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Contai nment Integrity........................

3/4 6-1 Primary Containment Leakage..........................

3/4 6-2 Primary Containment Air Locks........................

3/4 6-8 MSIV ' Leakage Control System..........................

3/4 6-10 Primary Containment Structural Integrity.............

3/4 6-11 Drywell and Suppression Chamber Internal Pressure....

3/4 6-12 Drywell Average Air Temperature......................

3/4 6-13 Drywell and Suppression Chamber Purge System.........

3/4 6-14 3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber..................................

3/4 6-15 Suppression Pool and Drywell Spray...................

3/4 6-18 Suppression Pool Cooling.............................

3/4 6-19 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES.................

3/4 6-20 i

3/4.6.4 VACUUM RELIEF Suppression Chamber - Drywell Vacuum Breakers........

3/4 6-48 Reactor Building - Suppression Chamber Vacuum

. Breakers...........................................

3/4 6-50 3/4.6.5 SECONDARY CONTAINMENT Secondary Containment Integrity.......................

3/4 6-51 Secondary Containment Automatic Isolatic., Dampers....

3/4 6-52 i

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Standby Gas Treatment System.........................

3/4 6-54 FERMI - UNIT 2 vii i

- -... - _ _ _ -... - _.. ~. -... -......

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE CONTAINMENT SYSTEMS (Continued) 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Drywell and Suppression Chamber Hydrogen Recoinoiner Systems............................................

3/4 6-57 Drywell and Suppression Chamber Oxygen Concentration.

3/4 6-58 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System...........

3/4 7-1 Emergency Equipment Cooling Water System.............

3/4 7-3 Emergency Equipment Service Water System.............

3/4 7-4 Diesel Generator Cooling Water System................

3/4 7-5 Ul timate Hea t S i n k...................................

3/4 7-6 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM.............

3/4 7-8 3/4.7.3 SHORE BARRIER PROTECTION.............................

3/4 7-11 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM................

3/4 7-14 3/4.7.5 SNUBBERS.............................................

3/4 7-16 3/4.7.6 SEALED SOURCE CONTAMINATION..........................

3/4 7-22 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fire Suppression Wa ter System........................

3/4 7-24 Spray and/or Sprinkler Systems.......................

3/4 7-27 CO Sy s t em s..........................................

3 / 4 7 -2 9 2

Ha l on Sy stems........................................

3 /4 7-3 0 Fire Hose Stations...................................

3/4 7-31 Yard Fire Hydrants and Hydrant Hose Houses.....,.....

3/4 7-36 3/4.7.8 FIRE RATED ASSENBLIES................................

3/4 7-38 3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND M0ISTURE SEPARATOR REHEATER.......................................-.....

3/4 7-40 FERMI - UNIT 2 viii Amendment No. 39 L..'.-.A A k9TP*%

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BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS...........................

B 3/4 7-1 l

3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM........

B 3/4 7-l' 3/4.7.3 SHORE BARRIER PR0TECTION........................

B 3/4 7-1

. 3 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM...........

B 3/4 7-1 3/4.7.5 SNUBBERS........................................

B 3/4 7-2 j

3/4.7.6.

SEALED SOURCE CONTAMINATION.....................

B 3/4 7-4 3/4.7.7 FIRE SUPPRESSION SYSTEMS........................

B 3/4 7-4 3/4.7.8 FIRE RATED ASSEMBLIES...........................

B 3/4 7 e 3/4.7.9

' MAIN TURBINE BYPASS SYSTEM AND MOISTURE SEPARATOR REHEATER..............................

B 3/4 7-5 3/4.8 ELECTRICAL' POWER SYSTEMS 3/4.8.1,3/4.8.2,and 3/4.8.3 A.C. SOURCES, D.C. SOURCES,.and ONSITE POWER DISTRIBUTION SYSTEMS............................

B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.........

B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH.............................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION.................................

B 3/4 9-1

'3/4.9.3.

CONTROL ROD P0SITION............................

B 3/4 9-1 3/4.9.4 DECAY TIME......................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS..................................

B 3/4 9-1 3/4.9.6 REFUELING PLATF0RM..............................

B 3/4 9-2 3/4.h.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L............

B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL I

and WATER LEVEL - SPENT FUEL STORAGE P00L.......

B 3/4 9-2 3/4.9.10 CONTROL R0D REM 0 VAL.............................

B 3/4 9-2

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3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION...

B 3/4 9-2 Amendment Nc. 39 FERMI - UNIT 2 xv 4

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' 3/4.10 SPECIAL TEST EXCEPTIONS

'3/4.10.1 PRIMARY CONTAINMENT INTEGRITY...................

B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM.....................

B 3/4,10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS.................

B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS.............................

B 3/4 10-1 3/4.10.5 OXYGEN CONCENTRATION............................

B 3/4 10-1 3/4.10.6 TRAINING STARTUPS...............................

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m; 6-POWER DISTRIBUTION' LIMITS-3/4.2.3: MINIMUM CRITICAL POWER RATIO l1 LIMITING CONDITION FOR OPERATION

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3.2.3 The MINIM _UM CRITICAL POWER RATIO (MCPR) shall be equal to'or-. greater than the MCPR limit shown in Figure 3.2.3-1 times the K shown'in Figure 3.2.3-2, i

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OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

< - ACTION a.

With MCPR less than the applicable MCPR limit shown in Figures 3.2.3-1 and 3.2.3-2, initiate corrective action within 15 minutes and restore MCPR to within the required limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ,

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With the main turbine bypass system and/or Moisture Separator Reheater

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inoperable per Specification 3.7.9, operation may continue and the provi-sions~of Specification 3.0.4 are not applicable provided that, within one hour, MCPR is determined to be equal to or greater than the MCPR limit as shown in Figure 3.2.3-1 by the main turbine. bypass and/or Moisture Separator

- Reheater inoperable curves times the applicable K shown in Figure 3.2.3-2.

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i SURVEILLANCE REQUIREMENTS-I i

i 4.2.3 MCPR, with:

t = 1.0 prior to performance of the initial scram' time measurements a.

for-the cycle in accordance'with' Specification 4.1.3.2, or b.

I as defined in Specification 3.2.3 used to determine the limit within 72. hours'of the conclusion ofieach scram time surveillance i

test required by Specification 4.1.3.2,.

shall.be determined to be equal'to or greater than the applicable'MCPR limit determined from Figures 3.2.3-1 and 3.2.3-2:

_ a.

.At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , l

b.

-Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 'after completion of a THERMAL POWER increase of at-least.15% of RATED THERMAL POWER, and c.

Initially ahd at least once.per:12 hours when the reactor is operating with a LIMITING CONTROL R0D PATTERN.for MCPR.

d.

The provisions of' Specification 4.0.4 are not applicable.

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e PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.7.8.2 Each of the above required fire doors shall be verified OPERABLE by inspecting the automatic hold-open, release and closing mechanism and latches at least once per 6 months, and by verifying:

a.

The OPERABILITY of the fire door supervision system for each electrically supervised fire door by performing a CHANNEL FUNCTIONAL TEST at least once per 31 days.

b.

The position of each locked-closed fire door at least once per 7 days.

I c.

That each unlocked fire door without electrical supervision is closed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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PLANT SYSTEMS 3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND MOISTURE SEPARATOR REHEATER l

LIMITING CONDITION FOR OPERATION 3.7.9 The main turbine bypass system and Moisture Separator Reheater shall be

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OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

ACTION:

With the main turbine bypass system and/or Moisture Separator Reheater inoperable, restore the system to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or take the ACTION required by Specification 3.2.3.

SURVEILLANCE REQUIREMENTS 4.7.9 The main turbine bypass system shall be demonstrated OPERABLE at least once per:

a.

92 days and during each COLD SHUTDOWN, by cycling each turbine bypass valve through at least one complete cycle of full travel, and b.

18 months by:

1.

Performing a system functional test which includes simulated I

automatic actuation and verifying that each automatic valve actuates to its correct position.

2.

Demonstrating TURBINE BYPASS SYSTEM RESPONSE TIME to be less than or equal to 300 milliseconds.

l FERMI - UNIT 2 3/4 7-40 Amendment No. 39

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B BASES TABLE B 3.2.1-1 SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOLANT ACCIDENT ANALYSIS Plant Parameters:

Core THERMAL P0WER....................

3430 MWt* which corresponds to 105% of rated steam flow Vessel Steam Output...................

14.86 x 108 lbm/hr which corresponds to 105% of rated steam flow l

I Vessel Steam Dome Pressure............

1055 psia l

Design Basis Recirculation Line Break Area for:

a.

Large Breaks 4.1 ft2 b.

Small Breaks 0.1 ft Fuel Parameters:

PEAK TECHNICAL INITIAL SPECIFICATION DESIGN MINIMUM LINEAR HEAT AXIAL CRITICAL FUEL BUNDLE GENERATION RATE PEAKING POWER

]

FUEL TYPE GE0 METRY (kW/ft)

FACTOR RATIO Initial Core 8x8 13.4

1. 4 1.18 l

J A more detailed listing of input of each model and its source is presented in Section II of Reference 1 and subsection 6.3 of the FSAR.

This power level meets the Appendix K requirement of 102%.

The core heatup calculation assumes a bundle power consistent with operation of the highest powered rod at 102% of its Technical Specification LINEAR HEAT GENERATION 1

RATE limit.

FERMI - UNIT 2 B 3/4 2-3' m-_-__-___m_____m_.-

POWER DISTRIBUTION LIMITS BASES j

.3/4.2.3 MINIMUM CRITICAL POWER RATIO The required operating limit MCPRs at steady-state operating conditions as specified in Specification 3.2.3 are derived from the established fuel cladding integrity Safety Limit MCPR of 1.06, and an analysis of abnormal operational transients.

For any abnormal operating transients analysis evaluation with the initial condition of the reactor being at the steady state operating limit, it is required that the resulting MCPR does not aecrease below the Safety Limit MCPR at any time during the transient assuming instrument trip setting given in Specification 2.2.

J To assure that the fuel cladding integrity Safety Limit is not exceeded during any anticipated abnormal operational transient, the most limiting transients have been analyzed to determine which result in the largest reduction in CRITICAL POWER RATIO (CPR).

The type of transients evaluated were loss of flow, increase in pressure and power, positive reactivity insertion, and coolant temperature decrease.

The limiting transient yields the largest delta MCPR. When added to the Safety Limit MCPR of 1.06, the required minimum operating limit MCPR of Specification 3.2.3 is obtained and presented in Figure 3.2.3-1.

The MCPR curves illustrated in Figure 3.2.3-1 were derived as described above for the following assumed operating conditions:

Curve A - MCPR limit with the main turbine bypass system and moisture separator reheater available.

This represents a total reactor steam flow bypass capability of approximately 36 percent.

Curve B - MCPR limit with the main turbine bypass system inoperative or moisture separator reheater inoperative.

This represents a total reactor steam flow bypass capability of approximately 10 percent or 26 percent, respectively.

Curve C - MCPR limit with both the main turbine bypass system and l

moisture separator reheater inoperative.

This represents no reactor steam flow bypass capability.

Curve A provides the MCPR limit assuming operation above 25 percent RATED THERMAL POWER with both the moisture separator reheater and main turbine bypass system operable.

The curve was developed based upon the operating MCPR limits for a Rod Withdrawal Error transient (UFSAR, Section 15.4.2) and a' Main Turbine Trip with Turbine Bypass Failure transient (UFSAR, Section 15.2.3).

The analysis of the Main Turbine Trip with Turbine Bypass Failure takes credit for the steam flow to the moisture separator reheater.

Curve B provides the MCPR limit assuming operation above 25 percent RATED THERMAL POWER with the moisture separator reheater operable and the main turbine bypass system inoperable.

The curve wa,s developed based upon the FERMI - UNIT 2 B 3/4 2-4 Amendment No.

39

POWER DISTRIBUTION LIMITS BASES i

MINIMUM CRITICAL POWER RATIO (Continued) operating MCPR limits for a Feedwater Controller Failure with Inoperable Turbine Bypass transient.

The analysis of the Feedwater Controller Failure transient also takes credit for steam flow to the moisture separator reheater.

Operation with the main turbine bypass inoperable or with a moisture separator reheater inoperable results in a total reactor steam flow bypass capability of approximately 10 percent and 26 percent, respectively.

The impact of operation with the moisture separator reheater inoperable but with bypass operable and utilization of Curve B is conservative because the 26 percent bypass capability is less limiting with regard to the existing analysis used to establish Curve B which assumes only 10 percent bypass capability (with the main turbine bypass system inoperable).

Therefore, the operation above 25 percent RATED THERMAL POWER with either the moisture separator reheater inoperable or main turbine bypass system inoperable is bounded by the existing Curve B.

Curve C provides the MCPR limit assuming operation above 25 percent RATED THERMAL POWER with both the moisture separator reheater and main turbine bypass system inoperable.

The curve was developed based upon the operating MCPR limits for a Feedwater Controller Failure with Inoperable Turbine Bypass transient assuming no steam flow through the moisture separator reheater.

There is no mode change restraint should the main turbine bypass or the moisture separator reheater be inoperable.

However, should the main turbine bypass system or the moisture separator reheater be inoperable as 25 percent RATED THERMAL POWER is exceeded, the MCPR check must be completed within one hour.

The evaluation of a given transient begins yith the system initial parameters shown in UFSAR Table 15.0-1 that are input to a GE-core dynamic l

behavior transient computer program.

The code used ta evaluate pressurization events is described in NED0-24154(3) and the program used in nonpressurization events is described in NED0-10802(2)

The outputs of this program along with the initial MCPR form the input for further analyses of the thermally limiting bundle with the single channel transient thermal hydraulic TASC code described in NEDE-25149(4)

The principal result of this evaluation is the reduction in MCPR caused by the transient.

The purpose of the K, factor of Fig ee 3.2.3-2 is to define operating limits at other than rated core flow conditions.

At less then 100% of reted flow the cequired MCPR is the product of the MCPR and the K factor.

The K f

f factors assure that the Safety Limit MCPR will not be violated during a flow increase transient resulting from a motor generator speed control failure.

The K factors may be applied to both manual and automatic flow control 7

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POWER DISTRIBUTION LIMITS BASES I

MINIMUM CRITICAL POWER RATIO (Continued)

The K factor values shown in Figure 3.2.3-2 were developed generically f

and are applicable to all BWR/2, BWR/3. and BWR/4 reactors.

The K, factors were derived using the flow control line corresponding to RATED THERMAL POWER at rated core flow.

For the manual flow control mode, the K factors were calculated such 7

that for the maximum flow rate, as limited by the pump scoop tube setpoint and the corresponding THERMAL POWER along the rated flow control line, the limiting bundle's relative power was adjusted until the MCPR changes with i

different core flows.

The ratio of the MCPR calculated at a given point of core flow, divided by the operating limit MCPR, determ'nes the K.

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' FERMI - UNIT 2 B 3/4 2-4b Amendment No.'39 l

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f PLANT SYSTEMS l

BASES 3/4.7.9 MAIN TURBINE BYPASS SYSTEM AND M0ISTURE SEPARATOR REHEATER The main turbine bypass system is an active bypass system designed to open the bypass valves in the event of a turbine trip to decrease the severity of the pressure transient.

Each valve is sized to pass a nominal 13 percent reactor steam flow in the full-open position for a controlled total bypass of approximately 26 percent reactor steam flow.

The main turbine bypass system is required to be OPERABLE consistent with the assumptions of the Feedwater Controller Failure analysis.

The primary purpose of the moisture. separator reheater is to improve cycle efficiency by using primary system steam to heat the high pressure turbine exhaust before it enters the low pressure turbines.

In doing so, it also provides a passive steam bypass flow of about 10 percent that mitigates the early effects of over pressure transients.

The moisture separator reheater is required to be OPERABLE consistent with the assumptions of the Main Turbine Trip with Turbine Bypass Failure analysis and the Feedwater Controller Failure analysis.

The operation with one or both of the main turbine bypasses inoperable or the moisture separator reheater inoperable to perform preventive or corrective maintenance above 25 percent RATED THERMAL POWER, requires, after one hour,

)

the evaluation of the MCPR in accordance with Specification 3.2.3.

If the MCPR is within the bounds established by Specification 3.2.3, power increases

'i to or operation above 25 percent RATED THERMAL POWER is allowed.

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FERMI - UNIT 2 B 3/4 7-5 Amendment No. 39

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