ML20247E842

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Proposed Tech Spec Pages Re Min Critical Power Ratio & Main Turbine Bypass Sys
ML20247E842
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 05/16/1989
From:
DETROIT EDISON CO.
To:
Shared Package
ML20247E835 List:
References
NUDOCS 8905260354
Download: ML20247E842 (11)
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Text

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4 Enclosure to-NIC-89-0083 -

Page 1

-t

, MCDIFIED TECHNICAL SPECIFICATION PAGE CHA!GES The proposed Technical Specification changes of Reference 2 have been modified as follows:-

1) Page 3/4 2-8. The title of Curve A has been changed to include the phrase "6M1 WITH MOIS7URE SEPARATOR REEEATER". This more l conpletely describes the necessary condition to use this curve.
2) Pages 3/4 7-40', B 3/4 7-5 (Insert) and Index pages viii and xv.

The title of Specification 3/4.7.9 is changed by adding the words "AND MOIS'IURE SEPARATOR REHFATER". This more conpletely describes 1 the scope of the revised Specification. The title change is. also made in the corresponding Bases section and in the Index.

3) Page B 3/4 2-4 (Insert) . The description of Curve B (in the first paragraph of the Insert) is modified to include both conditions for which Curve B applies rather than just the most limiting conditions upon which the Curve is based.
4) Page B 3/4 7-5 (Insert) - The' requirements for OPERABJTITY of the 4 main bypass system are clarified in regards to the rcident analyses assumptions'.

For completeness, the proposed page changes for the Reference 2 proposal as nodified are included in their entirety.

1

. 0905260354 DR 890510 ADOCK 0500034.1 PDC

. INDEZ LIMITING CONDITIONS FOR OPERATION AND 5'JRVEILLANCE REQUIREMENTS 1

{

PAGE SECTION CONTAINMENT SYSTEMS (Continued) f 3/4.6.6' PRIMARY CONTAINMENT ATMOSPHERE CONTROL Drywell and Suppression Chamber Hydrogen Recombiner Systems............................................ 3/4 6-57 Drywell and Suppression Chamber Oxygen Concentration. 3/4 6-SS {

l 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System........... 3/4 7-1 .

Emergency Equipment Co'o11ng Water System............. 3/4 7-3 H

Emergency Equipment Service Water System............. 3/4 7-4 Diesel Generator Cooling Water System................ 3/4 7-5 Ultimate Heat 51nk................................... 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 g l

)

3/4 7-14 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM. . . . . . . . . . . . . . . .

7-16 3/4.7.5 SNUBBERS..............................................'3/4 SEALED SOURCE CONTAMINATION.......................... 3/4 7-22 3/4.7.6 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System........................ 3/4 7-24 Spray and/or Sprinkler Systems. . . . . . . . . . . . . . . . . . . . . . . 3/4 7-27 CO Systems..........................................

3/4 7-29 2

Hal o n Sys tem s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 7-3 0 3/4 7-31 Fire Hose Stations...................................

Yard Fire Hydrants and Hydrant Hose Houses. . . . . . . . . . . 3/4 7-36 3/4.7.8 FIRE RATED ASSEMB LIES. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-38 T

3/4.7.9 MAIN TURBINE BYPASS SYSTEM.!MW. 0%.5. .HM..f?.CdMMf3/4 7-40 (EEHE ATs /t I

viii FERMI - UNIT 2

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i INDEX i

SASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS........................... B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM........ B 3/4 7-1 3/4.7.3 SMORE BARRIER PROTECTION........................ B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM. . . . . . . . . . . B 3/4 7-1 3/4.7.5 SNUBBERS........................................ B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION..................... B 3/4 7-4 3/4.7.7 rIRE SUPPRESSION SYSTEMS........................ B 3/4 7-4 3/4.7.8 FIRE RATED ASSEMBLIES........................... 8 3/4 7-4 3/4.7.9 .................... B 3/4 7-5 MAIN TURBINE BYPASS SYSTEM M O Mut E S{AvD EMM TOK REHEATEA 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 B 3/4 8-1 DISTRIBUTION SYSTEMS............................ .

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

3/4.9 REFUELING OPERATIONS REACTOR MODE SWITCH.............................

B 3/4 9-1 3/4.9.1 INSTRUMENTATION................................. B 3/4 9-1 3/4.9.2 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 COW 4UN I C ATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/4 9-2 3/4.9.6 REFUELING PLATF0RM..............................

3/4.9.7 CRANE TRAVEL-SPENT FUEL STORAGE P00L. . . . . . . . . . . . B 3/4 9-2 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL B 3/4 9-2 and WATER LEVEL - SPENT FUEL STORAGE P00L. . . . . . .

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

B 3/4 9-2

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

XV FERMI - UNIT 2 i

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POWER DISTRIBLTTION LIMITS p

3/4.2.3 MIN!m M CLITICAL POWER RATIO

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LIMITING E+3fTION FOR OPERATION i 3.2.3 The MINIMUM CRITICAL POWER RATIO (MCPR) shall beshown equal to in er greater Figure 3.2.3 2, than the MCPR limit shown in Figure 3.2.3-1 times the Kg with:

g, (Tave I)

B 14 - 2g where:

tg = 1.096 seconds, control rod average scram insertion time limit to notch 36 per Specificat'on 3.1.3.3, Yg = 0.852 + 1.65[

I h.06, ,

n N

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i=1 n

1

  • ave = i=1 "i i f

n 1 N l 11 i n = number of surveillance tests performed to date in cycle, ,

l th N g = number of active control rods h asured in the i surveillance test, 19 = average scram time to , notch 36 of all rods measured in the i th surve:111ance test, and I N = total number of active rods asasured in Specification '

3 4.1.3.2.a.

APPLICABILITY:

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

ACTION

a. With MCPR 1ess 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER wit n g g ho gs I With the main turbine bypass sys inoperable per Specification 3.7.9.

b.

operation may continue and the provisions 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 11 t as shown in Figure 3.2.3-1 shown byinthe sain 3.2.3-2. l Figure tuttine bypass inomerable cu ines the ap t.ed k w a W A* b M plicable K f FERMI - UNIT 2 3/4 2-6

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PLANT SYSTEMS 58 A#d/97o4 #EN e g rg4

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3/4.7.9 MAIN TURBINE BYPASS SYSTEM Mo Mor*71<RE LIMITING CGWDITION FOR OPERATION '

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3.7.9 The main' turbine bypass systemishall be OPERABLE.

OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or I

. APPLICABILITY:

regual to zu of RATED THERMAL POWER. ene d.,na Sisenmes Gehe.4.e inoperable, restore the system.to l ACTION: With the mair. turbine bypass sys ,

UPT EBLE status within I hour or take the ACTION required by Specification SURVEILLANCE REQUIREMENTS 1

4.7.9 The main turbine bypass' system shall be demonstrated CPERABLE at lel once per: I

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

)

b. 18 months by: '

1.

Performing a system functional test which includes simulated automatic actuation and verifying that each automatic valve actuates to its correct position.

2.

Demonstrating TURBINE BYPASS SYSTEH RESPONSE TIME to be les than or equal to 300 milliseconds.

4 3/4 7-40 FERMI - UNIT 2

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. 0 SWERDISTRIBUTIONLIMITS l

BASES 3/4.2.3 MINIMUM CRITICAL POWER RATIO The required operating 1 hit MCPAs at steady-state operating conditions as specified in Specification 3.2..i are derived from the established fuel cladding integrity Safety Limit MCPR of LO6, and an anatysis of abnormal operational transients. For any abnormal opercting 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 decrease below the Safety Limit MCPR at any time during the transient assuming instrument trip setting given' in Specification 2.2.

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 t loss of flow, increase in pressure and power, positive reactivity insert The limiting transient yields the largest and coolant temperature decrease.When added to the Safety Limit MCPR of 1.06, the required delta MCPR.

operating limit MCPR of Specification 3.2.3 is obtained and presented in n- Figure 3.2.3-1.

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The evaluation of a given transient begins with the system initial parameters shown in<MM Table < MD*4 that are input to a GE-core dynamicThe code behavior, transient computer program.

events is described in NEDO-24154I3) and the program used in nonpressur'ization The outputs of this program along with events is described in NEDO-10802(2) .

the initial MCPR form the input for further analyses of the thermally limiting bundle with the single channel transient thermal tydraulic TASC code described in NEDE-25149 I4} .

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

The purpose of the Kf factor of Figure 3.2.3-2 is to define operating limits at other than rated core flow conditions. At less than 100% of rated flow the required MCPR is the product of the MCPR and the Kg factor. The K g factors assure that the Safety Lf. nit MCPR will not be violated during a flowThe increase transient resulting frem a motor-generator speed control failure.

K factors may be applied to bo7.h manual and automatic flow control modes.

f The K, factor values shown ta Figure 3.2.3-2 were developed The K factors generically were and are applicable to all SWR /2, SWR /3, and 'dWR/4 reactors. f derived using the flow control line corresponding to RATED THERMAL POWER at rated core flow. '

For the manual flow control mode, the Kg factors were calculated such that i for the maximum flow rate, as limited by the pump scoop tube setpoint and the j corresponding THERMAL POWER along the rated flow control lire, the limiting bundle's telative power was adjusted until the MCPR changes with different core flows. The ratio of the MCPR calculated at a given point of core flow, divided by the operating limit MCPR, determines the Kf .

FERMI - UNIT 2 8 3/4 2-4 -

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I INSERT 20 PAGE B 3/4 2-4 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 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 PGER with both the moisture separator reheater and main turbine bypass system operable. The curve was developed based upon l the operating MCPR limits for a Rod Withdrawal Error transient (UFSAR, Seccion 15.4.2) and a Main Turbine Trip with Turbine Bypass Failure transient (UFSAR, Section 15.2.?; . The analysis of the Main Turbine  !

Trip with Turbine Bypass Failure takes credit for the steam flow to i the moisture separator reheater, i Curve B provides the MCPR limit assuming operation above 25 percent I RATED THERMAL PCWER with the moisture separator reheater operable and the 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. 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 TIIERMAL PWER with either the moisture separator reheater inoperable or main turbine bypass system inoperable is bounded by the existing Curve B.

1

)

98 INEERP 70 PAGE B 3/4 2-4 (cont.)

Curve C provides the KTR limit assuming operation above 25 percent RATED D115991 POWER with both the moisture separator reheater arx1 nain turbine bypass system inoperable. The curve was developed based upon the operating MCPR limits for a Feedwater Controller Failure with Inoperable Turbirse Bypass transient assuming no steam flow through the moisture separator reheater.

There is no node 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 DEINAL POWER is exceeded, the MCPR check nust be conpleted within one hour.

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PLANT SYSTEMS BASES ~

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I INSERT TO PAGE B 3/4 7-5 3/4 7.9 MAIN 'IURBITE BYPASS SYSTEM AfD MOIS'IURE SEPARATOR REHEATER 1

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 fril-open position for a controlled total bypass of approximately 26 perce 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 inprove cycle efficiency by using primary system steam to beat 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 THER4AL POWER, requires, after one hour, the evaluation of the MCPR in crcordance with Specification 3.2.3. If the MCPR is within the bounds established by Specification 3.2.3, power increases to or operation above 25 percent FATED THER4AL POWER is allowed.

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