B12531, Proposed Tech Specs,Amending Current Min Critical Power Ratio,Lhgr & MAPLHGR Operating Limits to Reflect Cycle 12 Operation.Affidavit Encl

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Proposed Tech Specs,Amending Current Min Critical Power Ratio,Lhgr & MAPLHGR Operating Limits to Reflect Cycle 12 Operation.Affidavit Encl
ML20214L660
Person / Time
Site: Millstone Dominion icon.png
Issue date: 05/21/1987
From:
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
Shared Package
ML19292H313 List:
References
B12531, NUDOCS 8706010044
Download: ML20214L660 (20)
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Text

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8 Docket No. 50-245 B12531 t

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- Attachment 1 i

Millstone Nuclear Power Station, Unit No.1  ;

,~ . Proposed Revision to Technical Specifications

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1.0 H. Minimum Critical Power Ratio (MCPR)

Minimum Critical Power Ratio (MCPR) is the value of critical power _

ratio associated with the most limiting assembly in the reactor core.

Critical Power Ratio (CPR) is the ratio of that power in a fuel-assembly, which is calculated by application of the GEXL correlation to cause some point in the assembly to experience boiling transition, to the actual assembly operating power.

I. Mode The reactor mode is that which is established by the mode-selector-switch.

J. Operable - Operability A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function ( s) . Implicit in this definition shall be the assumption ,

that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s) .

K. Operating Operating means that a system or component is performing its intended function in its required manner.

L. Operating Cycle Interval between the end of one refueling outage and the end of the next subsequent refueling outage.

M. Fraction of Limiting Power Density The ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR for that bundle type. The design LHGR is 13.4 kW/ft for BP8x8R (GE-7B) fuel bundles and 14.4 kW/ft for GE8x8EB (GE-8B) fuel bundles.

Maximum Fraction of Limiting Power Density l The Maximum Fraction of Limiting Power Density (MFLPD) is the highest value existing in the core of the Fraction of Limiting Power Density (FLPD).

N. Primary Containment Integrity Primary containment integrity means that the drywell and pressure suppression chamber are intact and all of the following conditions are satisfied.

Millstone Unit 1 1-2

LIMITING SAFETY SYSTEM SETTINGS (Continued) 2.1.2 FUEL CLADDING INTEGRITY A.1.b. MFLPD = maximum fraction of limiting power density where the limiting power density is 13.4 kW/ft for BP8x8R (GE-7B) fuel bundles and 14.4 kW/ft for GE8x8EB (GE-8B) fuel bundles.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.

c. During power ascensions with power levels less than or equal to 90%, APRM Flux Scram Trip Setting adjustments may be made as described below, provided that the change in scram setting adjustment is less than 10%

and, a notice of the adjustment is posted on the reactor control panel.

The APRM meter indication is adjusted by:

ARPRM = p

_FRP_

where:

APRM = APRM Meter Indication P = % Core Thermal Power For no combination of loop recirculation flow rate and core thermal power shall the APRM flux scram trip setting be allowed to exceed 120% of RATED THERMAL POWER.

2. APRM Reduced Flux Trip Setting (Refuel or Startup/ Hot Standby Mode)

When the mode switch is in the REFUEL or STARTUP/ HOT STANDBY position, the APRM scram shall be setdown to less than or equal to 15% of RATED THERMAL POWER. The IRM scram trip setting shall not exceed 120/125 of full scale.

Millstone Unit 1 2-4

LIMITING SAFETY SYSTEM SETTINGS (Continued) 2.1.2 FUEL CLADDING INTEGRITY B. 1. APRM Rod Block Trip Setting

a. The APRM rod block trip setting shall be as shown in Figure 2.1.2 and shall be: (Run Mode)

S *

S = Rod block setting in percent RB of rated thermal power (2011 MWt).

W = Total recirculation flow in percent of design. (Note 1, Page 2-3).

b. In the event of operation with a maximum fraction limiting power density (MFLPD) greater than the fraction of rated power (FRP),

the setting shall be modified as follows:

S FRP RB $( (0.58W + 50)

MFLPD where:

FRP = fraction of rated thermal power (2011 MWt)

MFLPD = maximum fraction of limiting power density where the limiting power density is 13 4 kW/ft for BP8x8R (GE-7B) fuel bundles and 14.4 kW/ft for GE8x8EB (GE-8B) fuel bundles.

The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the.

design value of 1.0, in which case the actual operating value will be used,

c. During power ascensions with power levels less than or equal to 90%, APRM Rod Block Trip Setting adjustments may be made as described below, provided that the change in scram setting adjustment is less than 10% and a notice of the adjustment is posted on the reactor control panel:

! Millstone Unit 1 2-5

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LIMITING CONDITION FOR OPERATION 3.11 REACTOR FUEL ASSEMBLY Applicability The Limiting Conditions for Operation associated with the fuel rods apply to those parameters which monitor the fuel rod operating conditions.

Objective The Objective of the Limiting Conditions for Operation is to assure the performance of the fuel rods.

Specifications A. Average Planar Linear Heat Generation Rate (APLHGR)

1. During power operation, the APLHGR for each type of fuel as a function of average planar exposure, shall be within limits based on applicable APLHGR limit values which have been approved for the respective fuel and lattice types. If hand calculations are required, the APLHGR for each type of fuel as a function of average planar exposure shall not exceed the limiting value for the most limiting lattice (excluding natural U) shown in Figure 3.11.1.

?. If at any time during operation it is determined by normal surveillance that the limiting value for APLHGR specified in Section 3.11.A.1 is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. If the APLHGR is not returned to within the prescribed limits within two (2) hours, 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 />. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

SURVEILLANCE REQUIREMENT 4.11 REACTOR FUEL ASSEMBLY Applicability The Surveillance Requirements apply to the parameters which monitor the fuel rod operating conditions.

Objective The Objective of Surveillance Requirements is to specify the type and frequency of surveillance to be applied to the fuel rods.

Millstone Unit 1 3/4 11-1

LIMITING CONDITION FOR OPERATION (continued)

Specifications A. Average Planar Linear Heat Generation Rate ( APLHGR)

The APLHGR for each type of fuel, as a function of average planar exposure shall be determined daily during reactor operation at 1 25% RATED THERMAL POWER.

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Millstone Unit 1 3/4 11-3

LIMITING CONDITION FOR OPERATION 3.11 REACTOR FUEL ASSEMBLY B. Linear Heat Generation Rate (LHGR)

During steady state power operation, the linear heat generation rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the maximum allowable LHGR of 13.4 kW/ft for BP8x8R (GE-7B) fuel bundles and 14.4 kW/ft for GE8x8EB (GE-8B) fuel bundles.

During power operation, the LHGR shall not exceed the limiting value. If at any time during operation it is determined, by normal surveillance, that the limiting value for LHGR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits. If the LHGR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought to COLD SHUTDOWN condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

SURVEILLANCE REQUIREMENT 4.11 REACTOR FUEL ASSEMBLY B. Linear Heat Generation Rate (LHCR)

The LHGR shall be checked daily during reactor operation at '25% RATED THERMAL POWER.

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Millstone Unit 1 3/4 11-4

LIMITING CONDITION FOR OPERATION 3.11 REACTOR FUEL ASSEMBLY C. Minimum Critical Power Ratio (MCPR)

During power operation, MCPR shall be as shown in Table 3.11.1. If at any time during operation it is determined by normal surveillance that the limiting value for MCPR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits.

If the steady state MCPR is not returned to within the prescribed limits within two (2) hours, 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 />. Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

s For core flows other than rated, the MCPRs in Table 3.11.1 shall be multiplied by K , where Kg is as shown in Figure 3 11.2.

7 f, D. If any of the limiting values identified in Specifications 3 11. A, B, or C, are exceeded, even if corrective action is taken, as prescribed, a Reportable Occurrence report shall be submitted.

SURVEILLANCE REQUIREMENT 4.11 REACTOR FUEL ASSEMBLY C. Minimum Critical Power Ratio (MCPR)

1. MCPR shall be determined daily during reactor power operation at

> 25% RATED THERMAL POWER and following any change in power level or distribution that would cause operation with a limiting control rod pattern as described in the bases for specification 3.3.8.5.

2. Utilization of Option B Operating limit MCPR values requires the scram time testing of 15 or more control rods on a rotating basis every 120 operating days.

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f 3 11 REACTOR FUEL ASSEMBLY BASES C. The steady state value for MCPR was selected to provide a margin to accomodate transients and uncertainties in monitoring the core operating state as well as uncertainties in the critical power correlation itself.

This value ensures that:

1. For the initial conditions of the LOCA analysis, a MCPR of 1.18 is satisfied. For the low flow ECCS analysis, an initial MCPR of 1.24 is assumed, and
2. For any of the special transients, or disturbances, caused by single operator error or single equipment malfunction the value of MCPR is conservatively assumed to exist prior to the initiation of the transient or disturbance.

At core thermal power levels s 25%, the reactor will be operating at minimum recirculation pump speed, and moderator void content will be very small. For all designated control rod patterns which may be employed at this power, thermal hydraulic analysis indicates that the resultant MCPR value is in excess of requirements. With this low void content, any inadvertent core flow increase would only place operation in a more conservative mode relative to MCPR. The daily requirement for calculation of MCPR at greater than 25% RATED THERMAL POWER is sufficient since power distribution shifts are very slow when there have not been significant power or control rod changes.

The use of the Option B operating limit MCPR requires additional SCRAM time testing and verification in accordance with GE letter, A. D. Vaughn to R. M. Matheny, April 21, 1987, regarding Potential Technical Specification Changes for Implementation of Advanced Methods. lv i

D. Reporting Requirements The LCO's associated with nonitoring the fuel rod operating conditions are required to be met at all times or corrected to within the limiting values of M4PLHGR, LHGR, and MCPR within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the time the plant is determined to be exceeding them. It is a requirement, as stated in Specifications 3.11. A, B, and C, that if at any time during power operation it is determined that the limiting values for MAPLHGR, LHGR, or MCPR are exceeded, action is then initiated to restore operation to within the prescribed limits. This action is to be initiated within 15 minutes if normal surveillance indicates that an operating limit has been reached.

Each event involving operation beyond a specified limit shall be logged and a reportable occurrence issued. It must be recognized that there is always an action which would return any of the parameters (MAPLHGR, LHGR, or MCPR) to within prescribed limits, namely power reduction. Under most circumstances, this will not be the only alternative.

Millstone Unit 1 B 3/4 11-2

GENERAL ELECTRIC C0MPANY AFFIDAVIT I, Rudolph Villa, being duly sworn, depose and state as follows:

1. I am Manager, Consulting Services, General Electric Company, and have been delegated the function of reviewing the information described in paragraph 2 which is sought to be withheld and have been authorized to apply for its withholding.
2. The information sought to be withheld is contained in l

" Loss-of-Coolant Accident Analysis Report for Millstone Unit i Nuclear Power Station, Supplement 1", NEDE-24085-1-P Supplement 1 j April 1987.

3. In designating material as proprietary, General Electric utilizes the definition of proprietary information and trade secrets set forth in the American Law Institute's Reststement of Torts, Section 757. This definition provides:

"A trade secret may consist of any formula, pattern, device or compilation of information which is used in one's business and which gives him an opportunity to obtain an advantage over competitors who do not know or use it.... A substantial 1 element of secrecy must exist, so that, except by the use of improper means, there would be difficulty in acquiring information.... Some factors to be considered in determining whethe given information is one's trade secret are: (1) the extent to which the information is known outside of his business; (2) the extent to which it is known by employees and others involved in his business; (3) the extent of measures taken by him to guard the secrecy of the information; (4) the value of the information to him and to his competitors; (5) the amount of effort or money expended by him in developing the information; (6) the ease or difficulty with the which the information could be properly acquired or duplicated by others."

4. Some examples of categories of information which fit into the definition of proprietary information are:
a. Information that discloses; a process, method or apparatus where prevention of its use by General Electric's competitors without license from General Electric constitutes a competitive economic advantage over other companies;
b. Information consisting of supporting data and analyses, including test data, relative to a process, method or apparatus, the application of which provide a competitive economic advantage, e.g., by optimization or improved marketability;
c. Information which if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality or licensing of a similar product;
d. Information which reveals cost or price information, production capacities, budget levels or commercial strategies of General Electric, its customers or suppliers;
e. Information which reveals aspects of past, present or future General Electric customer-funded development plans and programs of potential commercial value to General Electric;
f. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection;
g. Information which General Electric must treat as proprietary according to agreements with other parties.
5. Initial approval of proprietary treatment of a document is typically made by the Subsection manager of the originating component, the person who is most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge. Access 'to such documents within the Company is limited on a "need to know" basis and such documents are clearly identified as proprietary.
6. The procedure for approval of external release of such a document typically requires review by the Subsection Manager, Project Manager, Principal Scientist or other equivalent authority, by the Subsection Manager of the cognizant Marketing function (or delegate) and by the Legal Operation for technical content, competitive effect and determination of the accuracy of the proprietary designation in accordance with the standards enumerated above. Disclosures outside General electric are generally limited to regulatory bodies, customers and potential customers and their agents, suppliers and licensees then only with approoriate-protection by applicable regulatory provisions or ptoprietary agreements.
7. The document menticaed in paragraph 2 above has been evaluated in accordance with the above criteria and procedures and has been found to contain information which is proprietary and which is customarily. held in confidence by General Electric.
8. The document mentioned in paragraph 2 above is classified as proprietary because it contains details concerning current General Electric fuel designs which were developed at considerable expense to General Electric and which are not available to other parties.

1

9. The information to the best of my knowledge and belief has consistently been held in confidence by the General Electric Company, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties have been made pursuant to regulatory provisions of proprietary agreements which provide for maintenance of the information in confidence.
10. Public disclosure of the information sought to be withheld is likely to cause substantial harm to the competitive position of the General Electric Company and deprive or reduce the availability of project making opportunities because it would provide other parties, including competitors, with valuable information regarding current General Electric fuel designs which were obtained at considerable cost to the General Electric Company. The man power, computer and manufacturing resources expended by General Electric to develop the current fuel designs are valued at approxt:aately $8 million. In addition, the development of individual bundle and lattice designs require over 120 man-hours and approximately

$20,000 in computer resources.

STATE OF CALIFORNIA )) ss:

COUNTY OF SANTA CLARA Rudolph Villa, being duly sworn, deposes and says:

That he has read the foregoing affidavit and the matters stated therein are true and correct to the best of his knowledge, information, and belief.

Executed at San Jose, California, this 2 [ ay of 1987.

/

Ru'dolph Vill (

General Electric Company Subscribed and sworn before me thi y of $k 1987.

O b d . kh NOTARY PUBLIC, STATE OF CSIFORNIA PU U Y LL  ; tJOTARY PUBUC - CAUTORfJIA

% 4, SANTA CLARA C0"NTY

% My comm. expires JAN 13, 1989

. . . . . . . . _ . . ~ _ .

4 Docket No. 50-245 B12531  ;

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l Attachment 2 Millstone Nuclear Power Station, Unit No.1 General Electric Supplemental Reload Licensing Submitta!

May 1987 ]

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