ML052100159

License Amendment Application to Revise Technical Specification (TS) 3/4.10.2, Special Test Exceptions - Physics Tests

ML052100159
Person / Time
Site:	Davis Besse
Issue date:	07/27/2005
From:	Bezilla M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3095, LAR 04-0016
Download: ML052100159 (26)

Text

FENOC 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor. Ohio 43449 Mart B. Bezilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 Docket Number 50-346 10 CFR 50.90 License Number NPF-3 Serial Number 3095 July 27, 2005 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Davis-Besse Nuclear Power Station License Amendment Application to Revise Technical Specification (TS) 3/4.10.2, Special Test Exceptions - Physics Tests (License Amendment Request (LAR) 04-0016)

Ladies and Gentlemen:

Pursuant to 10 CFR 50.90, the following amendment is requested for the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS). The proposed amendment would revise Technical Specification (TS) 3/4.10.2, "Special Test Exceptions - Physics Tests," to increase the allowed time between the flux channel Channel Functional Tests and the beginning of Mode 2 Physics Tests from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Enclosure 1 to this letter contains the technical justification for these proposed changes and the proposed no significant hazards consideration determination. Enclosure 2 contains a list of regulatory commitments made in this letter.

FirstEnergy Nuclear Operating Company (FENOC) requests that this license amendment be approved by August 31, 2006. Once approved, the amendment will be implemented within 120 days.

The proposed changes have been reviewed by the DBNPS Plant Operations Review Committee and the Company Nuclear Review Board.

Should you have any questions or require additional information, please contact Mr. Henrys.

Hegrat, Supervisor - Fleet Licensing, at (330) 315-6944. cII l

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 2 The statements contained in this submittal, including its associated enclosures and attachments, are true and correct to the best of my knowledge and belief I am authorized by the FirstEnergy Nuclear Operating Company to make this submittal. I declare under penalty of perjury that the foregoing is true and correct.

Executed on: T-' 1) Xo By:__

Mark B. Bezilla, Vice Prq'sident-Nuclear MSH Enclosures cc: Regional Administrator, NRC Region III W. A. Macon, NRC/NRR Project Manager N. Dragani, Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

C. S. Thomas, NRC Region III, DB-1 Senior Resident Inspector Utility Radiological Safety Board

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 1 of 9 DAVIS-BESSE NUCLEAR POWER STATION EVALUATION FOR LICENSE AMENDMENT REQUEST NUMBER 04-0016

Subject:

License Amendment Application to Revise Technical Specification (TS) 3/4.10.2, Special Test Exceptions - Physics Tests

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration (NSHC) 5.2 Applicable Regulatory Requirements/Criteria

7.0 REFERENCES

8.0 ATTACHMENTS

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 2 of 9

1.0 DESCRIPTION

FirstEnergy Nuclear Operating Company (FENOC) requests amendment of the Davis-Besse Nuclear Power Station, Unit Number 1 (DBNPS) Facility Operating License Number NPF-3 Appendix A Technical Specifications (TS). The proposed amendment would revise Technical Specification (TS) 3/4.10.2, "Special Test Exceptions - Physics Tests," to increase the allowed time between the flux channel Channel Functional Tests and beginning of Mode 2 Physics Tests from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The time period provided by the revised Surveillance Requirement (SR) would then match corresponding information in the bases for NUREG-1430, Standard Technical Specifications - Babcock and Wilcox Plants(ISTS) 3.1.9, "PHYSICS TESTS Exceptions - MODE 2."

The existing Surveillance Requirement (SR) 4.10.2.2 requires that each Source Range, Intermediate Range, and High Flux channel be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to the start of PHYSICS TESTS. Under the existing SR, the CHANNEL FUNCTIONAL TEST is performed in anticipation of PHYSICS TESTS. However, PHYSICS TESTS are occasionally rescheduled due to plant conditions or administrative reasons, resulting in unnecessary repetition of the CHANNEL FUNCTIONAL TEST and further delays in initiating the required PHYSICS TESTS. The requested changes resolve this issue, while at the same time bringing TS 3/4.10.2 into closer alignment with the ISTS bases.

2.0 PROPOSED CHANGE

The proposed changes affect TS 3/4.10.2, "Special Test Exceptions - Physics Tests," as follows:

SURVEILLANCE REQUIREMENTS SR 4.10.2.2 states, "Each Source and Intermediate Range and High Flux Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to initiating PHYSICS TESTS." The requested change increases the time provided from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.0 BACKGROUND

The Nuclear Instrumentation System monitors reactivity conditions by detecting neutrons that leave the reactor core. The nuclear instruments monitor three overlapping ranges of flux: Source Range, Intermediate Range, and Power (high) Range. There are two electrically and physically independent source range channels in the Nuclear Instrumentation System. The Source Range instrumentation sensors are high sensitivity proportional counters that monitor neutron flux over a range of 1 x 10-1 to 1 x 106 counts per second. Control rod withdrawal is inhibited if the startup

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 3 of 9 rate in either channel exceeds 2 decades per minute. This interlock is not credited in any accident analysis.

The Intermediate Range instrumentation consists of two redundant channels that utilize gamma-compensated ion chambers as sensors. Each channel provides eight decades of flux level information, expressed by the logarithm of ion chamber current and startup rate. The ion chamber measuring range is from 1 x 1O-'1 to 1 x 10 3 amperes. A high startup rate of 3 decades per minute in either channel will inhibit control rod withdrawal. This interlock is not credited in any accident analysis.

The Power Range instrumentation consists of four redundant, linear channels that utilize uncompensated ion chambers as sensors. The channel output is directly proportional to reactor power and covers the range from 1% to 125% of rated power. The gain of each channel is adjustable, providing a means of calibrating the output against a reactor heat balance. In addition to indication, the Power Range instrumentation provides an input to the Reactor Protection System to perform safety functions including the High Flux reactor trip, and an input to the Integrated Control System for reactor control during normal operation.

Updated Safety Analysis Report (USAR) Section 7.8, "Nuclear Instrumentation (NI)," provides additional information on the design of this system. In addition, the High Flux reactor trip is credited in USAR Section 15.2.1, "Uncontrolled Control Rod Assembly Group Withdrawal From a Subcritical Condition (Startup Accident)," and USAR Section 15.2.2, "Uncontrolled Control Rod Assembly Withdrawal at Power."

The existing Surveillance Requirement (SR) 4.10.2.2 requires that each Source Range, Intermediate Range, and High Flux channel be subjected to a CHANNEL FUNCTIONAL TEST within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to the start of PHYSICS TESTS. Under the existing SR, the CHANNEL FUNCTIONAL TEST is performed in anticipation of PHYSICS TESTS. The required CHANNEL FUNCTIONAL TESTING is accomplished through sequential performance of eight surveillance procedures. The time required to complete these procedures leaves little margin to the end of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> window. The CHANNEL FUNCTIONAL TESTING performed on March 11, 2004 provides an illustration of this challenge: The eight surveillance procedures were sequentially performed over a period of eight hours, twenty-one minutes. An additional two hours, twenty-nine minutes of preparation was required prior to entering PHYSICS TESTING for TS 3.10.2. The combined time from the beginning of CHANNEL FUNCTIONAL TESTING to the beginning of PHYSICS TESTING was ten hours, fifty minutes. The limited margin available to the end of the 12-hour time window places an undue burden on plant personnel to synchronize the CHANNEL FUNCTIONAL TESTS with other activities, plant conditions, and administrative resources. In the example above, a delay of slightly greater than an hour would have required repetition of the CHANNEL FUNCTIONAL TESTS.

The purpose of the proposed amendment is to revise LCO 3.10.2, "Special Test Inspections" -

"PHYSICS TESTS" to reduce the potential for delay and test repetition described above.

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 4 of 9

4.0 TECHNICAL ANALYSIS

The proposed amendment would revise Technical Specification (TS) 3/4.10.2, "Special Test Exceptions - Physics Tests," to increase the allowed time between the flux channel Channel Functional Tests and beginning of Mode 2 Physics Tests from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The time period provided by the revised Surveillance Requirement (SR) would then match corresponding information in the bases for NUREG-1430, StandardTechnical Specifications - Babcock and Wilcox Plants (ISTS) 3.1.9, "PHYSICS TESTS Exceptions - MODE 2."

SURVEILLANCE REQUIREMENTS The requested change revises SR 4.10.2.2, pertaining to CHANNEL FUNCTIONAL TESTS, to increase the time period for performing the tests from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This change was evaluated by considering the requirements of TS 3/4.3.1, Reactor Protection System Instrumentation. TS 3/4.3.1 provides neutron flux instrumentation requirements for the various normal Modes of plant operation. TS Table 4.3-1, "Reactor Protection System Instrumentation Surveillance Requirements," indicates that the CHANNEL FUNCTIONAL TEST is not independently applicable for the source range, intermediate range, and high neutron flux monitors; however, CHANNEL FUNCTIONAL TESTING is incorporated into the required CHANNEL CALIBRATION. TS Table 3.3-1, "Reactor Protection System Instrumentation,"

provides the required number of operable channels and applicable Modes for each Reactor Protective System Functional Unit.

The "High Flux" Functional Unit (Functional Unit 2) CHANNEL FUNCTIONAL TEST is incorporated into the CHANNEL CALIBRATION, and a CHANNEL CHECK is required every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. In Mode 2, CHANNEL CALIBRATION is required at least once per 92 days.

The "Intermediate Range, Neutron Flux and Rate" Functional Unit (Functional Unit 10)

CHANNEL FUNCTIONAL TEST is incorporated into the CHANNEL CALIBRATION, and operators must verify within seven days prior to startup that at least one decade of overlap exists.

A CHANNEL CHECK is required every twelve hours in Mode 2. In Mode 2, a CHANNEL CALIBRATION is required at least once per 550 days.

The "Source Range, Neutron Flux and Rate" Functional Unit (Functional Unit 11) is required in Mode 2 until greater than 10-10 Amperes is observed on the Intermediate Range channels.

CHANNEL FUNCTIONAL TESTING is incorporated into the CHANNEL CALIBRATION, and operators must verify within seven days prior to startup that at least one decade of overlap exists. A CHANNEL CHECK is required every twelve hours in Mode 2, when this functional unit is required to be operable. The CHANNEL CHECK requirement begins in Mode 5 (increasing). In Mode 2, a CHANNEL CALIBRATION is required at least once per 550 days.

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 5 of 9 The CHANNEL CHECK performed for Functional Units 2, 10, and 11 consists of a qualitative assessment of channel behavior during normal operation. This determination includes, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. The CHANNEL CALIBRATION performed for Functional Units 2, 10, and 11 consists of an adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION encompasses the entire channel, except for the neutron detectors, and includes a CHANNEL FUNCTIONAL TEST.

Plant operating conditions immediately prior to PHYSICS TESTING are comparable to plant conditions immediately prior to STARTUP (Mode 2). The CHANNEL CALIBRATION intervals for STARTUP are all at least 92 days. Since the plant conditions immediately prior to PHYSICS TESTING are comparable to conditions immediately prior to STARTUP, and the proposed time to perform the pre-PHYSICS TEST CHANNEL FUNCTIONAL TEST is much less than the time currently allowed to perform CHANNEL FUNCTIONAL TESTING prior to STARTUP, FENOC believes that an extension of the time allowed to perform the pre-PHYSICS TEST CHANNEL FUNCTIONAL TEST from 12 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> would have no impact on plant operation. FENOC is aware of no conditions which would occur between 12 and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before the start of PHYSICS TESTING which would adversely affect the operability of the various flux channel Functional Units. Since the CHANNEL CHECK and CHANNEL CALIBRATION requirements of TS 4.3.1.1.1 remain in effect, performing a CHANNEL FUNCTIONAL TEST on each nuclear instrumentation Source and Intermediate Range and High Flux Channel within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to initiating PHYSICS TESTS, will continue to ensure that the instrumentation is OPERABLE shortly before PHYSICS TESTS begin and allows the operator to correct instrumentation problems that may be discovered during the testing.

5.0 REGULATORY SAFETY ANALYSIS 5.1 No Signiflcant Hazards Consideration The Nuclear Instrumentation System monitors reactivity conditions by detecting neutrons that leave the reactor core. The nuclear instruments monitor three overlapping ranges of flux: source range, intermediate range, and power range.

There are two electrically and physically independent source range channels in the Nuclear Instrumentation System. The source range instrumentation sensors are high sensitivity proportional counters that monitor neutron flux over a range of 1 x 10ol to I x 106 counts per second. Control rod withdrawal is inhibited if the startup rate in either channel exceeds 2 decades per minute. This interlock is not credited in any accident analysis.

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 6 of 9 The intermediate range instrumentation consists of two redundant channels that utilize gamma-compensated ion chambers as sensors. Each channel provides eight decades of flux level information, expressed by the logarithm of ion chamber current and startup rate. The ion chamber measuring range is from 1 x 10-, to 1 x 10- amperes. A high startup rate of 3 decades per minute in either channel will inhibit control rod withdrawal. This interlock is not credited in any accident analysis.

The power range instrumentation consists of four redundant, linear channels that utilize uncompensated ion chambers as sensors. The channel output is directly proportional to reactor power and covers the range from 1% to 125% of rated power. The gain of each channel is adjustable, providing a means of calibrating the output against a reactor heat balance. In addition to indication, the power range instrumentation provides an input to the Reactor Protective System to perform safety functions including the high flux reactor trip, and the Integrated Control System for reactor control during normal operation.

The proposed amendment would revise Technical Specification (TS) 3/4.10.2, "Special Test Exceptions - Physics Tests," to increase the allowed time between the flux channel Channel Functional Tests and beginning of Mode 2 Physics Tests from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The time period provided by the revised Surveillance Requirement (SR) would then match corresponding information in the bases for NUREG-1430, Standard Technical Specifications - Babcock and Wilcox Plants (ISTS) 3.1.9, "PHYSICS TESTS Exceptions - MODE 2."

An evaluation has been performed to determine whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The changes affect the Limiting Condition for Operation for "Special Test Exceptions - Physics Tests," in particular, the neutron flux instrumentation CHANNEL FUNCTIONAL TEST that must precede PHYSICS TESTING in MODE 2. The neutron flux instrumentation is not an accident initiator, but is credited for two events. These events are Uncontrolled Control Rod Assembly Group Withdrawal From a Subcritical Condition (Startup Accident), and Uncontrolled Control Rod Assembly Group Withdrawal at Power. The proposed change will not

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Enclosure I Page 7 of 9 impact the operation of the neutron flux instrumentation during these events. Consequently, the proposed changes will have no impact on the probability or consequences of any accident previously evaluated.

2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The changes affect the Limiting Condition for Operation for Refueling Operations - Instrumentation, in particular, the neutron flux instrumentation. The changes are only applicable in MODE 2. Under the proposed change, the neutron flux instrumentation will continue to operate in the same manner as previously considered. Accident initial conditions and assumptions remain as previously analyzed.

The proposed changes do not introduce any new or different accident initiators. In addition, the requested increase in the allowed time between the flux channel Channel Functional Tests and the beginning of Mode 2 Physics Tests from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> will not adversely impact the instrumentation's stability or capability. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

3. Does the proposed change involve a significant reduction in a margin of safety?

Response: No.

The changes affect the Limiting Condition for Operation for Refueling Operations - Instrumentation; in particular, the neutron flux instrumentation. The proposed changes to TS will not result in design changes to the neutron flux instrumentation or in changes to how the neutron flux instrumentation is used. As discussed in the response to question #1 above, channel operability will continue to be ensured by the CHANNEL CHECK and CHANNEL CALIBRATION requirements of TS 4.3.1.1.1. Therefore, the proposed change will not involve a significant reduction in a margin of safety.

Based on the above, it is concluded that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, there is a finding of"no significant hazards consideration."

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 8 of 9 5.2 Applicable Regulatorv Requirements/Criteria No applicable regulatory requirements were identified during preparation of this request.

In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, and would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Page 9 of 9

7.0 REFERENCES

1. DBNPS Operating License NPF-3, Appendix A Technical Specifications through Amendment 263.

2. DBNPS Updated Safety Analysis Report through Revision 24.

3. NUREG-1430, Revision 3, StandardTechnical Specifications - Babcock and Wilcox Plants.

8.0 ATTACHMENTS

1. Proposed Mark-Up of Technical Specification Pages

2. Proposed Retyped Technical Specification Pages

3. Technical Specification Bases Pages

Docket Number 50-346 License Number NPF-3 Serial Number 3095 PROPOSED MARK-UP OF TECHNICAL SPECIFICATION PAGE (1 mark-up page and "8 information-only" pages follow.

TS 3/4.3.1 is provided for information only.

Page 3/4 3-6 is not provided because it is blank.)

SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITING CONDITION FOR OPERATION 3.10.2 The limitations of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.2, 3.1.3.5, 3.1.3.6, 3.1.3.7, and 3.1.3.9 may be suspended during the performance of PHYSICS TESTS provided:

a. The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and

b. The reactor trip setpoints on the OPERABLE High Flux Channels are set at < 25% of RATED THERMAL POWER.

c. The nuclear instrumentation Source Range and Intermediate Range high startup rate control rod withdrawal inhibit are OPERABLE.

APPLICABILITY: MODE 2.

ACTION:

With the THERMAL POWER > 5% of RATED THERMAL POWER, immediately open the control rod drive trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be < 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.2.2 Each Source and Intermediate Range and High Flux Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 244-2 hours prior to initiating PHYSICS TESTS.

DAVIS-BESSE, UNIT I 3/4 10-2 Amendment No. 33,

INFORMATION ONLY 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTEC-nON SYSTEM INSTRUMENTATION LIRITING CONDmON FOR OPERAT1ON 33.1.1 As a minimum, the Reactor Protection System instumentation cbannels and shutdown bypasscs of Table 3.3-1 shall be OPERABLE.

APPLICLABLTY: As sbown in Table 3.3-1.

AC0TIN:

As shown in Table 3 3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each Reactor Protection System insturnctation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.

43.1.1 2 The shutdown bypass function shall be demonstrated OPERABLE at least once per REFUELING INTERVAL during CHANNEL CALBRATION tesdig of each channel affectd by shutdown bypass opcfli.cm 43.1.13 The REACTOR PROTECTION SYSTEM RESPONSE Tll&vE of each reactor tip function shall be demonstrated to be within its limit at lcast once per REFUELING INTERVAL.

Neutron detectors are exempt from response time testing; the response time of the neutron flux signal portion of the channel shall be measured from the neutron detector output or from the input of the firt clectronic component in the cbancL Each test shall include tt least one channel per function micb that all chancls arc tested at least once every N times the REFUELING INTERVAL where N is the total number of redundant channels in a specific rtactor trip function Ls shown in the ¶Total No. ofChannels" column ofTable 33-1.

T* c response timcs include the sensor (except for the neutron dttectors), Reactor Protction System instrumcnt delay, and the control rod drive breaker delay. A delay time has been assumed for the Reactor Coolant Pumnp monitor in the detcrmination of the response time of the H-igh Flux/Number of Reactor Coolant Pumps On functional uni DAVIS-BESSE, UNIT 1 3/4 3-1 Amendment No, 218, 225; -259

TABLE33 PROTECTION SYSTEM INSTRUMENTATION 0

MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UHIT OF CHANNELS TO TRIP_ OPERABLF MODES ACTIO rn 1. Manual Reactor Trip 2 1 2 1, 2 and

• 1l z 2. High Flux 4 2 3 1, 2 201,10

- 3. RC High Temperature 4 2 3 1, 2 3#, 10

4. Flux - tFlux - Flow 4 2(a)(b) 3 1, 2 20, 10

5. RC Low Pressure 4 2(a) 3 1, 2 311,10

6. RC High Pressure 4 2 3 1. 2 La

~ 7. RC Pressure-Temperature 4 2(a) 3 1, 2 3#, 10

• 8. High Flux/Number of Reactor Coolant Pumps On 4 2(a) (b) 3 1. 2 30, 10

9. Containment High Pressure 4 2 3 1, 2 311, 10

10. Intermediate Range, Neutron Flux and Rate 2 N/A 2(c) 1, 2 and

• 4

11. Source Range, Neutron Flux and Rate A. Startup 2 N/A 2 2t1 and

• 5 3 B. Shutdown 2 N/A 3, 4 and 5 6 Z

12. Control Rod Drive Trip Breakers 2 per trip 1 per trip 2 per 1. 2 and

• 70, 81 system trip system a, 0 system 9 13. Reactor Trip Module 2 per trip system I per trip system 2 per trip system 1, 2 and

• 7# 0 m 14. Shutdown Bypass High Pressure 4 2 3 2**. 3** 61 4** 5**

300 Mc

15. CR Relays 2 2 2 1, 2 and

• I-0

INFORMATION ONLY TABLE 3.3-1 {Continued)

TAIBLE _OTAILON

• With the .control rod drive trip breakers in the closed position and the control rod drive system capable of rod withdrawal.

• • When Shutdown Bypass is actuated.

IThe provisions bf Specification 3.0.4 are not applicable.

fWiHgh voltage to detector may be de-energized above lo"' amps on both Intermediate.Range charnels.

(a) Trip may be manually bypassed when RCS pressure < 1820 psig *by actuating Shutdown Bypass provided that:

(1) The High Flux Trip Setpoint is < 5% of RATED THERMAL POWER, (2) The Shutdown Bypass High Pressure Trip Setpoint of S 1820 psig is imposed, and (3) The Shutdown Bypass is reroved when.RCS pressure > 1B20 psig.

(b) Trip may be manually bypassed when Specification 3.10.3 is in effect.

(c) The minimum channels OPERABLE requirement may be reduced to one when Specification 3.10.1 or 3.10.2 is in effect.

ACTION STATEMENTS ACTION I - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the control rod drive trip breakers.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels STARTUP and/or POWER OPERATION may proceed provided both of the following conditions are satisfied:

a. The inoperable channel is placed in the bypassed or tripped condition within one hour.

b. Either, THERMAL POWER is restricted to < 75% of RATED [

THERMAL POWER and the High Flux Trip Setpoint is reduced tn

< 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the Q'AZN'.uT POWER TILT is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

DAVIS-BESSE, UNIT I 3/4 3-3 Amendment No.185

TABLE 3.3-1 (Continued) INFORMATION ONLY ACTION STATEMENTS (Continued)

ACTION 3 - With the number of OPERABLE channels one less than the Total xumber of Channels STARTUP and POWER OPERATION may proceed provided Ihe Jnoperable.chanen..ls placed In the bypissed or tripped condition within one hour.

ACTION 4 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. < 5% of RATED THERMAL POWER restore the inoperable-channel to OPERABLE status prior to increasing THERMAL POWER above 5% of RATED THERMAL POWER.

b. > 5% of RATED THERMAL POWER, POWER OPERATION may continue.

DAVIS-BESSE, UNIT I 3 /4 3-4 Anendment No. J3$185

INFORMATION ONLY TABLE 3.3-1 (Continued)

ACTION STATEKEhTS (Continued)

ACTION S - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and vith the TEERIAL POVER level:

a. <10 10 amps on the Intermediate Range (IR) instru-mentation, restore the inoperable chmnnel to OPM LE status prior to increasing THERMAL POVER above 10 amps on the IR instrumentation.

b. > 10 10 amps on the IR instrumentation, operation may continue.

ACTION 6 - Uith the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 vithin one hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

ACTION 7 - With the number of OPERAILE channels one less than the Total Number of Channels STARTUP and/or POYER OPERATION may proceed provided all of the folloving conditions are satisfied:

a. Within 1 hour:

1. Place the inoperable channel in the tripped condition.

or

2. Remove power supplied to the control rod trip device associated vith the inoperative channel.

b. One additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1. and the inoperable channel above may be bypassed for up to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period vhen necessary to test the trip breaker associated vith the logic of the channel being tested per Specification 4.3.1.1.1. The inoperable channel above may not be bypassed to test the logic of a channel of the trip system associated vith the inoperable channel.

DAVIS-BESSE, UNIT 1 3/4 3-5 Amendment No. AUY, 135 (Next page is 3/4 3-Sa.)

TABLE 3.3-1 (Continued)

ACTION STATEMENTS LContinued1 ACTION 8 With one of the Reactor Trip Breaker diverse trip features (undervoltage or shunt trip devices) inoperable, restore it to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the breaker in trip in the next hour.

ACTION 9 With one or both channels of SCR Relays inoperable, restore the charnels to OPERABLE status during the next COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 10 With the number of channels OPERABLE one less than the Kinimum Channels OPERABLE requirement, within one hour, place one inoperable channel in trip and the second inoperable channel in bypass, and restore one of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and open the reactor trip breakers.

INFORMATION ONLY 3/4 3-Sa Amendment NoJ30s;85 DAVIS-BESSE, UNIT I (Next page is 3/4 3-6.)

.1 0 TABLE-4.3-1 REACTOR PROTECTIOIJ YSTEM TNStRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL )DES IN WHICH CHANNE L CHANNEL FUNCTIONAL SURVEILLANCE mt fUNCTIONAL UNIT CHECKy CALIBRATI --TEST _ AEQUIREQ

1. Manual Reactor Trip N.A. N.A. S/U(1) N.A._

2. High Flux S D(2), and Q(6,9) N.A. 1,.2 S.F.,

3. RC High Temperature S R SA(9) 1,2 0

4. Flux - AFlux - Flow S(4) M(3) and Q(6,7,9) N.A. 1, 2

5. RC Low Pressure S R SA(9) 1, 2

6. RC High Pressure S R SA(9) 1, 2

7. RC Pressure-Temperature S R SA(9) 1, 2 S. High Flux/Number of Reactor Coolant Pumps On S Q(6,9) N.A. 1, 2 0 E SA(9) 1, 2

9. Containment High Pressure S

10. Intermediate Range, Neutron 1, 2 and*

Flux and Rate S E(6) N.A. (5)

11. Source Range, Neutron Flux tU.A. (5) 2, 3, 4 and 5 and Rate S E(6)

N.A. H.A. Q(8,9) and S/U(i)(8) 1, 2 and*

12. Control Rod Drive Trip Breakers N.A. Q(9) 1, 2 and*

13. Reactor Trip Module Logic N.A.

R SA(9) 2**, 3**, 4**, 5**

14. Shutdown Bypass High Pressure S N.A. R 1, 2 and *

15. SCR Relays N.A.

TABLE 4.3-1 (Continued) INFORMATION ONLY VOTATIO1 (1) - If not performed in previous 7 days.

(2) - Heat balance only, above 15% of RATED THERMAL POWER.

(3) - When THERMAL POWER (TP] is above 50% of RATED THERMAL POWER [RTP]

and at a steady state, compare out-of-core measured AXIAL POWER IMBALANCE [API 0] to incore measured AXIAL POWER IMBALANCE [API 1]

as follows:

RTP (API0 - API] - Offset Error TP Recalibrate if the absolute value of the Offset Error is ? 2.5%.

(4) - AXIAL POWER IMBALANCE and. loop flow indications only.

(5) - CHANNEL FUNCTIONAL TEST is not applicable. ..Verify at least one decade overlap prior to each reactor startup if not verified in previous 7 days.

(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) - Flow rate measurement sensors may be excluded from CHANNEL CALIBRATION. Howcver, each flow measurement sensor shall be calibrated at least once each REFUELING INTERVAL.

(8) - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of both the undervoltage and shunt trip devices of the Reactor Trip Breakers.

(9) - Performed on a STAGGERED TEST BASIS.

• - With any control rod drive trip breaker closed.

- When Shutdown Bypass is actuated.

DAVIS-BESSE, UNIT 1 3/4 3-8 Amendment No. 42,1OB,1!,1w,1S. 218

)

Docket Number 50-346 License Number NPF-3 Serial Number 3095 PROPOSED RETYPED TECHNICAL SPECIFICATION PAGE (1 page follows)

a SPECIAL TEST EXCEPTIONS PHYSICS TESTS LIMITING CONDITION EOR OPERATION 3.10.2 The limitations of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.2, 3.1.3.5, 3.1.3.6, 3.1.3.7, and 3.1.3.9 may be suspended during the performance of PHYSICS TESTS provided:

a. The THERMAL POWER does not exceed 5% of RATED THERMAL POWER, and

b. The reactor trip setpoints on the OPERABLE High Flux Channels are set at < 25% of RATED THERMAL POWER.

c. The nuclear instrumentation Source Range and Intermediate Range high startup rate control rod withdrawal inhibit are OPERABLE.

APPLICABILITY: MODE 2.

ACTION:

With the THERMAL POWER > 5% of RATED THERMAL POWER, immediately open the control rod drive trip breakers.

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined to be < 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

4.10.2.2 Each Source and Intermediate Range and High Flux Channel shall be subjected to a CHANNEL FUNCTIONAL TEST within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to initiating PHYSICS TESTS.

DAVIS-BESSE, UNIT 1 3/4 10-2 Amendment No. 33,

Docket Number 50-346 License Number NPF-3 Serial Number 3095 TECHN'ICAL SPECIFICATION BASES PAGE (1 page follows)

Note: The Bases page is providedfor information only.

a INFORMATION- ONLY 3/4.10 SPECIAL TEST EXCEPTIONS BASES 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS This special test exception permits individual control rods to be positioned outside of their specified group heights and insertion limits and to be assigned to other than specified control rod groups, and permits AXIAL POWER IMBALANCE and QUADRANT POWER TILT limits to be exceeded during the performance of such PHYSICS TESTS as those required to 1) measure control rod worth, 2) determine the reactor stability index and damping factor under xenon oscillation conditions and 3) calibrate AXIAL POWER IMBALANCE and QUADRANT POWER TILT instrumentation.

3/4.10.2 PHYSICS TESTS This special test exception permits PHYSICS TESTS to be performed at less than or equal to 55 of RATED THERMAL POWER and is required to verify the fundamental nuclear characteristics of the reactor core and related instrumentation.

3/4.10.3 REACTOR COOLANT LOOPS This special test exception permits reactor criticality under various flow conditions and is required in order to perform certain startup and PHYSICS TESTS while at low THERMAL POWER levels.

3/4.10.4 SHUTDOWN MARGIN This special test exception provides that a minimum amount of con-trol rod worth is immediately available for reactivity control when tests are performed for control rod worth measurement. This special test exception is required to permit the periodic verification of the actual versus predicted core reactivity condition occurring as a result of fuel burnup or fuel cycling operations.

DAVIS-BESSE, UNIT 1 B 3/4 10-1

Docket Number 50-346 License Number NPF-3 Serial Number 3095 Enclosure 2 COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY THE DAVIS-BESSE NUCLEAR POWER STATION (DBNPS) IN THIS DOCUMENT. ANY OTHER ACTIONS DISCUSSED IN THE SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY THE DBNPS. THEY ARE DESCRIBED ONLY FOR INFORMATION AND ARE NOT REGULATORY COMMITMENTS. PLEASE NOTIFY HENRY L. HEGRAT, SUPERVISOR - FLEET LICENSING (330-315-6944) OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

I COMMITMENTS l DUE DATE I None I Not Applicable