Text

Amend 107 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Reload Core
	ML20155B450
Person / Time
Site:	Maine Yankee
Issue date:	09/27/1988
From:	Wessman R; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20155B444	List: ML20155B440; ML20155B450; ML20155B463;
References
	NUDOCS 8810060308
	Download: ML20155B450 (16)
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UNITED STATES i

! ># NUCLEAR REGULATORY COMMISSION

% W ASHING To N, D. C. 20666

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MAIFE YANrEE ATOMIC POWER COMPANY COCKET NO. 50-309 '

P MAINE YANrEE ATOMIC POWER STATION l

AMENCMENT TO FACILITY OPERATING LICENSE

, Ainendment No.107

License No. OPR-36 e

l l 1. The Nuclear Regulatory Comission (the Comission) has found that: i j A. *The appiteation for amendment by Maine Yankee Atomic Power

Company (the licensee), dated June 30, 1988, as supplemented on August 2,1988, complies with the standards and requirernents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and reguletions set forth in 10 CFR Chapter I;

) B. The facility will operate in conformity with the application, j the provisions of the Act, and the rules and regulations of .

i the Conrnission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the .5ealth !

j and safety of the public, and (ii) that such activities will be i conducted in compliance with the Comission's regulations; '

D. The issuance of this amendrent will not be inimical to the comon ;

defense and security or to the health and safety of the public; j and

E. The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requireenents

, have been satisfieo.

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachrent to this license '

arendment. and paragraph 2.B(6)(b) of Facility Operating License ;

No. OPR-36 is hereby arended to read as follows: i (b) Technical Specifications The Technical Specifications contained in Appendix A. l as revised through Amendment No.107 . are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificatters. l f

3. This license amendment is effective November 1.1988. ;

I l FOR THE NUCLEAR REGULATORY Com!SSION i m i THer w I Richard H. Wessman. Director !

Proiect Directorate I-3 ;

Division of Reactor Projects I/I!

Attachment:

Changes to the Technical ,

Specifications [

Date of Issuance: Se,oteber 27, 1988 l

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e ATTACHMENT TO LICENSE AMENDMENT NO.107 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Remove Pages Insert Pages 2.2-1 2.2.-l 3.10-2 3.10-2 3.10-3 3.10-3 3.10-4 3.10-4 3.10-5 3.10-5 3.10-9 3.10-9 3.10-12 3.10-12 3.10-13 3.10-13 3.10-15 3.10-15 3.10-16 3.10-16 3.10-17 3.10-17 3.10-18 3.10-18 3.10-19 3.10-19 3.10-20 ----

4

i l

2.2 SAFETY LIMITS - REACTOR CORE I Aeolicability Applies to the limiting combinations of reactor power, and Reactor Coolant System flow, temperatare, and pressure during operation.

Objective To maintain the integrity of the fuel cladding and prevent the release of significant amounts of fission products to the reactor coolant.

Soecifications A. The reactor and the Reactor Protection System shall be operated such that the following Specified Acceptable Fuel Design Limit (SAFDL) on the departure from nucleate boiling heat flux ratio (DNBR) is not exceeded during normal operation and anticipated operational occurrences.

DNBR - 1.20 using the YAEC-1 DNB heat flux correlation B. The reactor and the Reactor Protection System shall be operated such that the following SAFDLs for prevention of fuel centerline melting are not exceeded during normal operation and anticipated operational occurrences.

A steady-state peak linear heat generation rate (LHGR) equal to:

Fuel Tvoe LHGR Limit. kw/ft E E .

H,L 20.8 20.2 N 21.2 20.2 P 22.3 21.1 Q 23.2 22.2 where the LHGR limit for each fuel type decreases linearly with Cycle Average Burnup (CAB), and the EOC Burnup for the purposes of establishing a linear relationship is 14,500 E D/HTU CAB.

BAlli !

l To maintain the integrity of the fuel cladding, thus preventing fission '

product release to the Primary System, it is necessary to prevent overheating of the cladding. This is accomplished by operating within the nucleate boiling regime of heat transfer, and with a peak linear heat rate that will not cause fuel centerline melting in any fuel rod. First, by operating within the nucleate boiling regime of heat transfer, the heat transfer coefficient is large enough so that the maximum clad surface temperature is only slightly greater than the coolant saturation temperature. The upper boundary of the nucleate boiling regime is termed "Departure from Nucleate Boiling" (DNB). At this point, there is a sharp reduction of the heat transfer coefficient, which would result in higher cladding temperature and the possibility of cladding failure. ,

2.2-1

/cendment No. 29,S,7/,N,Q,#,107

. 4. If the CEA deviation alarms from both the computer pulse counting system and the reed switch indication system are not available, individual CEA positions shall be logged and misalignment checked every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

5. Operation of the CEA's in the automatic mode is not permitted.

B. shutdown Margin Limits

1. When the reactor is critical, the shutdown margin will not be less than that shown in Figure 3.10-7. except during low power physics tests when the shutdown margin will not be less than 2% in reactivity.

2. A trippable CEA is considered inoperable if it cannot be tripped.

A CEA that cannot be driven shall be assumed not able to be tripped

, until it is proven that it can be tripped. Operation with an inoperable CEA is permitted provided:

a. The shutdown margin specified in 3.10.8.1 is satisfied without the reactivity associated with the inoperable CEA within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of identificat 'n of the inoperable CEA.

b. Except for low power physics tests and CEA exercises, only one CEA is inoperable.

3. A trippable CEA is considered to be a slow CEA if the drop time from de-energizing its holding coil to reaching 90% of its full insertion exceeds 2.7 seconds at operating temperature and 3 pump flow.

Operation with a slow CEA is permitted provided:

a. The shutdown margin specified in 3.10.B.1 is satisfied without 1.5 times the reactivity associated with the slow CEA after 2.5 seconds of drop time.

C. Power Distribution Limits

1. The peak linear heat rate with appropriate consideration of normal flux peaking, measurement-calculational uncertainty (8%), engineering factor (3%), increase in linear heat rate due to axial fuel densification and thermal expansion (0.3% for Type E only) and power measurement uncertainty (2%) shall not exceed the limits shown in Figure 3.10-11 as a functio.1 of core height. l Should any of these limits be exceeded. immediate action will be

, taken to restore the linear heat rate to within the appropriate limit specified in Figure 3.10-11.

l 3.10-2 Amendment No. 38, AD, $5, 68, 98,107

l

. 2. the to9a1 radial peaking factor, defined as I T P FR"FR (1 + Tq )

shall be evaluated at least once a month during power operation above 50% of rated full power.

2.1 FR is the latest available anrodded radial peak determined from the incore monitoring system for a condition where all CEAs are at or above the 100% po'ver insertion limit. Tq is given by the following expression:

. Tq = 2 (Ps-Pc)2 + (Pb-Pd)2 Da+Pb + Pc+Pd)Z where Pi is the relative quadrant power determined from the incore system for quadrant i, when the incore system is operable. If the incore system is not operable, the Pi are the signals from excore detector channels 1.

T 2.2 If the measured value of FR 'txceeds the value given in Figure 3.10-4 perform one of the following within 24 haurs:

1. Reduce the allowable PDTL insertion (Figure 3.10-1) symmetric offset LCO (Figures 3.10-8 and 3.10-9) and trip band (Figure 2.1-2), thermal margin low pressure trip limit (Figures 2.1-1 a and b and Technical Specification 2.1), linear heat rate limits 1

(Figure 3.10-11) and excore LOCA monitoring limits (Figures 3.10-2 and 3.10-3) by a factor greater than or equal to: l T

(FR measured] / (F Figure 3.10-4]

i 08:

2. Reduce thermal power at a rate of at least 1%/ hour to bring the combination of thermal power and % increase in F R to

within the limits of Figure 3.10-5, while maintaining CEAs ,

at or above the 100% power insertion limit. Reduce the '

linear heat rate limits (Figure 3.10-11) and, if incores are not operable and Figure 3.10-2 is in use, then also reduce excore LOCA monitoring limit (Figure 3.10-2) by a factor greater than or equal to:

T T (FR measured] / (FR Figure 3.10-4]

08:

3. Be in at least HOT SHUT 00HN.

3.10-3 _

1 Amendment No. /M, M, S, 4, M, N,107 l

i

3. Incore detector alarms shall be set at least weekly.

Alarms will be based on the latest power distribution obtained, so that the linear heat rate does not exceed the linear heat rate limit defined in Specification 3.10.C.1. If four or more coincident alarms are received, the validity of the alarms shall be immediately determined and, if valid, power shall be immediately decreased below the alarm setpoint.

3.1 If the incore monitoring system becomes inoperable, perform one of the following within 4 effective full power hours:

1. Initiate a power reduction at a rate of at least 1% per hour to a power level less than or equal to the power level given by the following expression for the limiting location:

P - [R-1.1 SJ (LHR (limit)/ LHR (measured)], where: j P - % of rated power, R - 79 for symmetric offset between +0.05 and 0.10, or 85 for symmetric offset between 0.00 and 0.05, or 93 for symmetric offset between 0.00 and -0.05, or 89 for symetric offset between -0.05 and -0.10.

S - Number of steps the CEAs deviates from the CEA position evisting when the linear heat rate measurement was taken.

LHR (limit) - Linear heat rate permitted by Specification 3.10.C.1, and LHR (measured) - Linear heat rate last measv ed corrected to l 100% oower.

The CEAs shall be maintained above the 100% power dependent insertion limit and synynetric offset shall be monitored once per shift to ensure that it remains within the above range.

This method may be used for up to 14 effective full power days from the time when the linear heat rate measurement was taken; or

2. Comply with the LCO given in Figure 3.10-2 while maintaining the CEAs above the 100% power insertion limit.

If a power reduction is required, reduce power at a rate of at least 1% pwer hour; or

3. Comply with the LCO in Figure 3.10-3. If a power reduction is required, reduce power at a rate of at least 1% per hour.

3.10-4 1 I

1 Amendment No. 36, M, 65, 78, 95, M2,107

4.2 If the measured value of Ta is greater tha 0.10, operation may proceed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months as long as F is maintained within the provisions of Specification 3.1.C.2. Subsequent operation for the purpose of measurement and to identify the cause of the tilt is allowable provided:

1. The thermal power level is restricted to less than or equal to 207. of the maximum allowable thermal power level for the existing Reactor Coolant Pump combination, and

2. Reduce setpoints in accordance with Specification 3.10.C.2.2.

5. The incore detector system shall be used to confirm power distribution, such that the peaking assumed in the safety analysis is not exceeded, after initial fuel loading and after each fuel reloading, prior to operation of the plant at 50% of rated power.

6. If the core is operating above 50% of rated power with an excore nuclear channel out of service, then the azimuthal power tilt shall be determined once per shift by at least one of the following means:

a. Neutron detectors (at least 2 locations per quadrant).

b. Core-exit thermocoupl's (at least 2 thermocouples per quadrant).

7. Whenever the reactor is operating above 20% of rated power of the l excore symmetric offset shall be within the bounds for symetric offset LCO shown in Figure 3.10-8. l When the turbine is operating in the IMPIN control mode, the excore symmetric offset shall be within the bounds for symetric offset LOC shown in Figure 3.10-9.

l

0. Moderator Temperature Coefficient (HTC):

Except during low power physics testing the MTC shall be less positive than that shown in Figure 3.10-10. l E. Coolant Conditions

1. Except for low power physics testing, the reactor coolant pressure and the reactor coolant temperature at the inlet to the reactor vessel shall be maintained within the limits of Figure 3.10-6 during steady-state operation whenever the reactor is critical.

2. Except for low power physics testing, the reactor coolant flow rate shall be maintainej at or more than a nominal value of 360,000 gpm during steady-state operation whenever the reactor is critical.

Egention: The requirements of 3.10.E.2 may be modified during initial testing to permit power levels not to exceed 10% of rated power with three loops operating on natural circulation.

3.10-5 Amendment No. 38, /0, 65, 68, 78, 107 ,

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NOTE: 1. THIS CURVE INCLUDES 10% CALCULAT10NAL UNCERTAINTY

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MAINE YANKEE Allowable Power Level vs. Increase in Figure Technical Total Radial Peak 3.10 - 5 Specification 1 l

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