ML042170068

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Application for Technical Specification Change Regarding Combustible Gas Control Systems (License Amendment Request No. 03-0021)
ML042170068
Person / Time
Site: Davis Besse 
Issue date: 07/29/2004
From: Bezilla M
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
3044
Download: ML042170068 (28)
v • d • e


Text

s-ENOC"%%

5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Mark B. Bezilla.

419-321-7676 Vice President-Nuclear Fax: 419-321-7582 Docket Number 50-346 1 0CFR50.90 License Number NPF-3 Serial Number 3044 July 29, 2004 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Davis-Besse Nuclear Power Station Application for Technical Specification Change Regarding Combustible Gas Control Systems (License Amendment Request No. 03-0021)

Ladies and Gentlemen:

In accordance with the provisions of 10 CFR 50.90, the FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the Technical Specifications (TS) for the Davis-Besse Nuclear Power Station (DBNPS), Unit 1.

The proposed amendment would delete the TS requirements related to the combustible gas control systems. The following TSs are affected: TS 3/4.6.4.1, "Hydrogen Analyzers"; TS 3/4.6.4.3, "Containment Hydrogen Dilution System"; TS 3/4.6.4.4, "Hydrogen Purge System";

and TS 6.8.4.f, "Ventilation Filter Testing Program (VFTP)". FENOC will maintain a hydrogen monitoring system capable of diagnosing beyond design-basis accidents, and will relocate requirements regarding the hydrogen analyzers to the DBNPS Updated Safety Analysis Report (USAR) Technical Requirements Manual, following NRC approval of this license amendment and concurrent with its implementation.

The proposed amendment is based on the changes to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on October 16, 2003. The 10 CFR 50.44 rule changes eliminated the requirements for hydrogen recombiners and hydrogen purge systems, and relaxed the requirements for hydrogen and oxygen monitoring equipment to make them commensurate with their risk significance. The final nile publication (68 FR 54123 dated September 16, 2003) recognized that some plants have

Docket Number 50-346 License Number NPF-3 Serial Number 3044 Page 2 hydrogen vent and purge systems that backup the hydrogen recombiners, and that these backup systems were also no longer required. At the DBNPS, the hydrogen analyzers, Containment Hydrogen Dilution System, and Hydrogen Purge System presently provide the combustible gas control function and have requirements in the Operating License TSs. The elimination of the TS requirements relative to the hydrogen analyzers, Containment Hydrogen Dilution System, and Hydrogen Purge System is consistent with the intent of the final rule.

The proposed changes are also consistent with the intent of Revision I of NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the Federal Register on September 25, 2003 (68 FR 55416), as part of the Consolidated Line Item Improvement Process (CLIIP). As with the 10 CFR 50.44 final rule publication, the model Safety Evaluation included with the CLIlP recognized that the reasoning for the elimination of the need for the hydrogen recombiners also applied to hydrogen vent and purge systems.

In order for the DBNPS to accrue the benefits afforded by the rule change in a timely manner, approval of the proposed amendment is requested by August 1, 2005. Once approved, the amendment shall be implemented within 120 days.

The proposed changes have been reviewed by the DBNPS onsite and offsite review committees.

Should you have any questions or require additional information, please contact Mr. Gregory A. Dunn, Manager - Regulatory Affairs, at (419) 321-8450.

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 _

_A__

MKL Enclosures

Docket Number 50-346 License Number NPF-3 Serial Number 3044 Page 3 cc:

Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR Senior Project Manager D. J. Shipley, 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 3044 Enclosure I DAVIS-BESSE NUCLEAR POWER STATION DESCRIPTION AND ASSESSMENT FOR LICENSE AMENDMENT REQUEST NUMBER 03-0021 (23 pages follow)

LAR 03-0021 Page 1 DAVIS-BESSE NUCLEAR POWER STATION DESCRIPTION AND ASSESSMENT FOR LICENSE AMENDMENT REQUEST NUMBER 03-0021

Subject:

Application for Technical Specification Change Regarding Combustible Gas Control Systems.

1.0 INTRODUCTION

2.0 DESCRIPTION

OF PROPOSED AMENDMENT

3.0 BACKGROUND

4.0 REGULATORY REQUIREMENTS AND GUIDANCE

5.0 TECHNICAL ANALYSIS

6.0 REGULATORY ANALYSIS

6.1 Verification and Commitments 7.0 NO SIGNIFICANT HAZARDS CONSIDERATION 8.0 ENVIRONMENTAL EVALUATION 9.0 PRECEDENT

10.0 REFERENCES

11.0 ATTACHMENTS

LAR 03-0021 Page 2

1.0 INTRODUCTION

The proposed amendment is based on the changes to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on October 16, 2003. The 10 CFR 50.44 rule changes eliminated the requirements for hydrogen recombiners and hydrogen purge systems, and relaxed the requirements for hydrogen and oxygen monitoring equipment to make them commensurate with their risk significance. The final rule publication (68 FR 54123 dated September 16, 2003) recognized that some plants have hydrogen vent and purge systems that backup the hydrogen recombiners, and that these backup systems were also no longer required. At the Davis-Besse Nuclear Power Station, Unit Number 1 (DBNPS), the hydrogen analyzers, Containment Hydrogen Dilution System, and Hydrogen Purge System presently provide the combustible gas control function and have requirements in the Operating License Technical Specifications (TSs). The elimination of the TS requirements relative to the hydrogen analyzers, Containment Hydrogen Dilution System, and Hydrogen Purge System is consistent with the intent of the final rule.

The proposed changes are also consistent with the intent of Revision I of NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the Federal Register on September 25, 2003 (68 FR 55416), as part of the Consolidated Line Item Improvement Process (CLIIP). As with the 10 CFR 50.44 final rule publication, the model Safety Evaluation included with the CLIIP recognized that the reasoning for the elimination of the need for the hydrogen recombiners also applied to hydrogen vent and purge systems.

2.0 DESCRIPTION

OF PROPOSED AMENDMENT The proposed amendment would delete the TS requirements related to the combustible gas control systems. TS 3/4.6.4.1, "Hydrogen Analyzers", TS 3/4.6.4.3, "Containment Hydrogen Dilution System", and TS 3/4.6.4.4, "Hydrogen Purge System", would be deleted in their entirety. In addition, TS 6.8.4.f, "Ventilation Filter Testing Program (VFTP)", would be revised to remove requirements related to the Hydrogen Purge System. Related to these changes, administrative changes to pages VI and XI of the TS Index are also proposed.

3.0 BACKGROUND

The background for this application is addressed by the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are addressed by the NRC Notice of Availability published on September 25, 2003 (68 FR 55416),

LAR 03-0021 Page 3 TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

5.0 TECHNICAL ANALYSIS

FENOC has reviewed the Nuclear Regulatory Commission (NRC) staffs safety evaluation (SE) published on September 25, 2003 (68 FR 55416) as part of the CLIIP Notice of Availability.

This verification included a review of the NRC staffs SE, as well as the supporting information provided to support TSTF-447. FENOC has concluded that the information presented in the TSTF proposal and the SE prepared by the NRC staff are applicable to the DBNPS and support this amendment for the incorporation of the changes to the DBNPS TS.

6.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

6.1 Verification and Commitments As discussed in the NRC staff's model SE published in the Federal Register on September 25, 2003 (68 FR 55416) for this TS improvement, FENOC is making the following verifications and regulatory commitments:

1.

FENOC has verified, as discussed below, that a hydrogen monitoring system capable of diagnosing beyond design-basis accidents is installed at the DBNPS and is making a regulatory commitment to maintain that capability.

The hydrogen monitoring system installed at the DBNPS is safety grade and has a measurement capability of hydrogen concentration over a range of 0 to 10%. This range was previously approved by the NRC as acceptable, and remains sufficient to support this license amendment application.

In the event the hydrogen monitoring system was not available, hydrogen concentration can be determined via the post-accident sampling system (PASS). It is noted that FENOC is pursuing a separate licensing amendment application that would allow elimination of the PASS.

However, this license amendment application would require FENOC to develop contingency plans for obtaining and analyzing highly radioactive samples from the containment atmosphere. Hence, the capability to analyze containment atmosphere samples for hydrogen concentration would be maintained.

LAR 03-0021 Page 4 Draft Regulatory Guide DG-1 117, "Control of Combustible Gas Concentrations in Containment," describes methods acceptable to the NRC staff for implementing the 10 CFR 50.44 rule change. As stated in Section C.2.1 of DG-1 117, safety-related hydrogen monitoring systems installed and approved by the NRC prior to the effective date of the rule are sufficient to meet the criteria that equipment for monitoring hydrogen must be functional, reliable, and capable of continuously measuring the concentration of hydrogen in the containment atmosphere following a design-basis accident for accident management, including emergency planning.

The DBNPS sample pumps utilized in the hydrogen monitoring system, due to pressure limitations, are not capable of being placed into service until several hours following an accident. Attachment 6 to Item II.F.1 of NUREG-0737, "Clarification of TMI Action Plan Requirements," requires that the hydrogen monitors be capable of operating within 30 minutes of initiation of safety injection. Section C.2.1 of DG-1 117 notes that the 30 minute requirement can be overly burdensome and describes a method for licensees to adopt a risk-informed functional requirement in lieu of the 30 minute requirement. Final resolution of this variance is being addressed under the DBNPS corrective action process.

The requirements for maintaining a hydrogen monitoring system capable of diagnosing beyond design-basis accidents as described above will be included in the DBNPS USAR Technical Requirements Manual. This regulatory commitment will be implemented concurrent with the proposed amendment implementation.

2.

The DBNPS does not have an inerted containment.

7.0 NO SIGNIFICANT HAZARDS CONSIDERATION FENOC has reviewed the proposed no significant hazards consideration determination published on September 25, 2003 (68 FR 55416) as part of the CLIIP. FENOC has concluded that the proposed determination presented in the notice is applicable to the DBNPS and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).

8.0 ENVIRONMENTAL EVALUATION FENOC has reviewed the environmental evaluation included in the model SE published on September 25, 2003 (68 FR 55416) as part of the CLIIP. FENOC has concluded that the staffs findings presented in that evaluation are applicable to the DBNPS and the evaluation is hereby incorporated by reference for this application.

LAR 03-0021 Page 5 9.0 PRECEDENT This application is being made in accordance with the CLIIP. FENOC is not proposing variations or deviations from the TS changes described in TSTF-447 or the NRC staffs model SE published on September 25, 2003 (68 FR 55416) other than those differences related to the use of hydrogen vent and purge systems in lieu of installed hydrogen recombiners, and other than format differences between the DBNPS TS and the Improved Standard Technical Specifications for Babcock and Wilcox Plants. A license amendment in accordance with the CLIIP was issued by the NRC for the Beaver Valley Power Station on May 19, 2004 (Reference 6).

1

0.0 REFERENCES

1.

DBNPS Operating License NPF-3, Appendix A Technical Specifications through Amendment No. 262.

2.

DBNPS Updated Safety Analysis Report through Revision 23.

3.

Notice of Availability of Model Application Concerning Technical Specification Improvement to Eliminate Hydrogen Recombiner Requirement, and Relax the Hydrogen and Oxygen Monitor Requirements for Light Water Reactors Using the Consolidated Line Item Improvement Process, published September 25, 2003 (68 FR 55416).

4.

Industry/TSTF Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors".

5.

Final Rule, Combustible Gas Control in Containment, published September 16, 2003 (68 FR 54123).

6.

NRC letter dated May 19, 2004, "Beaver Valley Power Station, Unit Nos. 1 and 2

-Issuance of Amendments re: Elimination of Hydrogen Recombiners and Hydrogen Monitors (TAC Nos. MC1869 and MC1870)".

11.0 ATTACHMENTS

1.

Proposed Mark-Up Of Technical Specification Pages

2.

Proposed Retyped Technical Specification Pages

LAR 03-0021 PROPOSED MIARK-UP OF TECHNICAL SPECIFICATION PAGES (8 pages follow)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity..............................

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

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

3/4 6-6 Internal Pressure.................................

3/4 6-7 Air Temperature.................................

3/4 6-8 Deleted......................................

3/4 6-9 Containment Ventilation System.........................

3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System............................

3/4 6-11 Containment Cooling System...........................

3/4 6-13 3/4.6.3 CONTAINMENT ISOLATION VALVES...................

3/4 6-14 3/4.6.4 COMBUSTIBLE GAS CONTROLD&edd I-ydrogen Analyzers.

'/ 6 23 T'%-1-+-A

')

1 A

r-Containmn t II)drogcn Dilution System..

Hydrogen Purge S stem.

3/4.6.5 SHIELD BUILDING Emergency Ventilation System.

Shield Building Integrity.

Deleted....

3/4 6 25

/464 3/4 6-28 3/4 6-31 3/4 6-32 DAVIS-BESSE, UNIT I VI Amendment No. 38, 66, 135, 205,

INDEX BASES SECTION 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...........

3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS.............

3/4.6.3 CONTAINMENT ISOLATION VALVES...................

3/4.6.4 COMBUSTIBLE GAS COWROL.

-.Deted 3/4.6.5 SHIELD BUILDING..............................

PAGE B 3/4 6-1 B 3/4 6-2 B 3/4 6-3 B3/146 I

B 3/4 6-4 DAVIS-BESSE, UNIT I XI Amendment No.

GCONMTANMENT SYSTEIKS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN AALYZERS LWITPIG CONDITION FOR OPERATION 3.6.1.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACION:

a. With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days 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 />.
b. With both hyderogn analyzers inoperable, r-re at least one analyzer to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-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 />.

cT ml nn rn T A \\Tf^T7 D T..

T TmD ToxXT 4.6.4.1 Eaeh hydrogen analyzer shall be demonstrated OPERABLE at least once per 31 days by perfonmanec of a CHAb14IEL CHECK.

4.6.4.2 Each hydrogen analyzer shall be demonstrated OPERABLE at Icast once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL-ALRmA-TION using sample gases eenaining:

a. Zero volume percent hydrogen, balance nitrogen, and
b. 2.5 + 0.5 volume percent hydrogen, balance nitrogen.

DELETED DAVIS-BESSE, UNIT 1 3/4 6-23 Amendment No. 167, 168,

CONTAIPWENT SYSTEMS LIMITING CONDITION FOR OPERATION I___ _

3!1 _.- _

inAdeendent ontainment hdorogen diultion systems shall be OPERABLE.

r

-- w --

APPLICABILITY: MODES I and 2.

AGPON-i

a. With one eontainment hydrogen dilution system inoperablc, restore the inoperable system to OPERABLE status within 30 days 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 />.
b. With both containment hydrogen dilution systems inoperable, restore at least one dilution system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> er be in at least HOT STA-nBY within the nex.At 6 heus SURVTEILLANCE RPQUIRPMRTUST I

... I I....

Il 1_

J T

T'TM A T T T? _. l___.

&4.0.45. Eafn ecntainment nyarogen oiluiton system shall be aemonstraten UP'LRABLLE at least T' A T'T!TI lI T

-A tI...

once per Y4 U-ays En a t :

v uii'OU z 1 EMSIS Dy:

a. Verifying. that the sstemcan bestadedn operator-action in thee cntro r-oom, and
b. V'erifying that thessystem operates for at least 15 minutes and the blower develops a discharge pressure of 15 psig.

I DAVIS-BESSE, UNIT I 3/4 6-25 Amendment No. 183,

COTAWAMIHT SYSTEMS HYDROGEN PURGE SYSTEM LINMITING CONDITION FOR OPERATION 3.6.4.4 A containment hy dfogen purge sy stem shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With the containment hydrogen purge system inopefable, rcstere the hydregen purge systemrto OPERABLE status within 30 days or bc in at least HOT STANDBY within thc next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SUMYELTTANGE REQUIRMEM-IPrS 4.6.4.4 The hydrogen purge system shall be demonstrated OPERABLE:

a. At least once eaoh 18 mon adsorbers and verifying th
b. At least onec each 18 mcn Pfeg-at PnrP)

I H

ths by initiating nlew, through the JEPA filters and eharc at the system operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> vAith the heatei ths and in aceor-danee with the Ventilation Filtf Testing Ma I'sen.

i I

D1ELETED DAVIS-BESSE, UNIT I 3/4 6-26 Amendment No. 155, 209, 244,

CONTAINMENT SYSTEMS SURVEILANC-13R lOUIREUMENTS (Continued)

e. 4Deletedl
d. [Deleted]
e.

[Deleted]

DE[Deleted]

DELETEDI DAVIS-BESSE, UNIT 1 3/4 6-27 Amendment No. 155, 209, 244,

ADMINISTRATIVE CONTROLS 6.8.4 (Continued)

e. Radiological Environmental Monitoring Program (Continued)
3)

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

f. Ventilation Filter Testing Program (VFTP):

A program shall be established to implement the following required testing of safety related filter ventilation systems in accordance with Regulatory Guide 1.52, Revision 2*,

ANSI/ASME N510-1980, and ASTM D 3803-1989.

1.

Demonstrate for each of the safety related systems that an in-place test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass

< 1% when tested in accordance with Regulatory Guide 1.52, Revision 2 and ANSI/ASME N510-1980 at the system flowrate specified below, +/- 10%.

Safety Related Ventilation System Flowrate Containment Hydrogen Purge System 100 ofm Shield Building Emergency Ventilation System 8000 cfm Control Room Emergency Ventilation System 3300 cfm

2.

Demonstrate for each of the safety related systems that an in-place test of the charcoal adsorber shows a penetration and system bypass < 1% when tested in accordance with Regulatory Guide 1.52, Revision 2 and ANSI/ASME N510-1980 at the system flowrate specified below, +/-10%.

Safety Related Ventilation System Flowrate Containment Hydrogen Purge System 100 0cfml Shield Building Emergency Ventilation System 8000 cfm Control Room Emergency Ventilation System 3300 cfm

3.

Demonstrate for each of the safety related systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified

  • The periodic testing for the Shield Building Emergency Ventilation System and the Control Room Emergency Ventilation System are performed once each REFUELING INTERVAL. The need for testing following painting, a fire, or a chemical release in any ventilation zone communicating with the Containment Hydrogen Purgc System, the -Shield Building Emergency Ventilation System; or the Control Room Emergency Ventilation System is as specified by the VFTP. The method of testing is based on Regulatory Guide 1.52, Revision 2, except for charcoal laboratory testing which will be performed in accordance with ASTM D 3803-1989.

DAVIS -BES SE, UNIT I 6-14c Amendment No. 170, 244,

ADMINISTRATIVE CONTROLS 6.8.4 (Continued)

f.

Ventilation Filter Testing Program (VFTP) (Continued) below when tested in accordance with ASTM D 3803-1989 at a temperature of 300 C and the relative humidity (RH) specified below.

Safety Related Ventilation System Penetration RH Containment Hydrogen Purge System 5 2.5%

700 Shield Building Emergency Ventilation System

< 2.5%

95%

Control Room Emergency Ventilation System

< 2.5%

70%

4.

Demonstrate for each of the safety related systems that the pressure drop across the combined HEPA filters, the prefiltersl, and the charcoal adsorbers is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2 and ANSIIASME N510-1980 at the system flowrate specified below,

+/- 10%.

Safety Related Ventilation System Delta P Flowrate Containment Hydrgen Purge System 25 inches Water Gauge 100 efI Shield Building Emergency Ventilation System 6 inches Water Gauge 8000 cfhi Control Room Emergency Ventilation System 4.4 inches Water Gauge 3300 cfm

  • Containment Hydrogen Purge does not contain prefilters.
5.

Demonstrate that the heaters for the safety related Containment Hydrogen Purgc System dissipate 2000 watts 4/ 20%0° when tested in accordance with ANSMASME N510 1980.

The provisions of SR 4.0.2 and SR 4.0.3 are applicable to the VFTP test frequencies.

DAVIS-BESSE, UNIT 1 6-14d Amendment No. 244,

LAR 03-0021 PROPOSED RETYPED TECHNICAL SPECIFICATION PAGES (8 pages follow)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity..............................

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

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

3/4 6-6 Internal Pressure.................................

3/4 6-7 Air Temperature.................................

3/4 6-8 Deleted......................................

3/4 6-9 Containment Ventilation System.........................

3/4 6-10 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System.....

3/4 6-11 Containment Cooling System...........................

3/4 6-13 3/4.6.3 CONTAINMENT ISOLATION VALVES.....

3/4 6-14 3/4.6.4 Deleted 3/4.6.5 SHIELD BUILDING Emergency Ventilation System..........................

3/4 6-28 Shield Building Integrity.............................

3/4 6-31 Deleted......................................

3/4 6-32 DAVIS-BESSE, UNIT I VI Amendment No. 38, 66, 135, 205,

INDEX BASES SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT.........................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS...

B 3/4 6-2 3/4.6.3 CONTAINMENT ISOLATION VALVES...................

B 3/4 6-3 3/4.6.4 Deleted l

3/4.6.5 SHIELD BUILDING..............................

B 3/4 6-4 DAVIS-BESSE, UNIT I XI A mend ment N o.

DELETED I

DAVIS-BESSE, UNIT I 3/4 6-23 Amendment No. 167, 168,

DELETED I

DAVIS-BESSE, UNIT I 3/4 6-25 Amendment No. 183,

DELETED I

DAVIS-BESSE, UNIT 1 3/4 6-26 Amendment No. 155, 209, 244,

DELETED I

DAVIS-BESSE, UNIT I 3/4 6-27 Amendment No. 155, 209, 244,

ADMINISTRATIVE CONTROLS 6.8.4 (Continued)

e. Radiological Environme'ntal Monitoring Program (Continuiedj
3)

Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

f. Ventilation Filter Testing Program (VFTP):

A program shall be established to implement the following required testing of safety related filter ventilation systems in accordance with Regulatory Guide 1.52, Revision 2*,

ANSIIASME N510-1980, and ASTM D 3803-1989.

1. Demonstrate for each of the safety related systems that an in-place test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass

< 1% when tested in accordance with Regulatory Guide 1.52, Revision 2 and ANSI/ASME N510-1980 at the system flowrate specified below, +/- 10%.

Safety Related Ventilation System Flowrate Shield Building Emergency Ventilation System 8000 cfm l

Control Room Emergency Ventilation System 3300 cfm

2.

Demonstrate for each of the safety related systems that an in-place test of the charcoal adsorber shows a penetration and system bypass < 1% when tested in accordance with Regulatory Guide 1.52, Revision 2 and ANSI/ASME N510-1980 at the system flowrate specified below, +/-10%.

Safety Related Ventilation System Flowrate Shield Building Emergency Ventilation System 8000 cfm Control Room Emergency Ventilation System 3300 cfm

3.

Demonstrate for each of the safety related systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified

DAVIS-BESSE, UNIT 1 6-14c Amendment No. 170, 244,

ADMINISTRATIVE CONTROLS.

6.8.4 (Continued)

f.

Ventilation Filter Testing Program (VFTP) (Continued) below when tested in accordance with ASTM D 3803-1989 at a temperature of 300 C and the relative humidity (RH) specified below.

Safety Related Ventilation System Penetration RH Shield Building Emergency Ventilation System

< 2.5%

95%

Control Room Emergency Ventilation System

  • 2.5%

70%

4.

Demonstrate for each of the safety related systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2 and ANSI/ASME N510-1980 at the system flowrate specified below,

+1-10%.

Safety Related Ventilation System Delta P Flowrate Shield Building Emergency Ventilation System 6 inches Water Gauge 8000 cfm Control Room Emergency Ventilation System 4.4 inches Water Gauge 3300 cfm The provisions of SR 4.0.2 and SR 4.0.3 are applicable to the VFTP test frequencies.

DAVIS-BESSE, UNIT I 6-14d Amendment No. 244,

Docket Number 50-346 License Number NPF-3 Serial Number 3044 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 THE MANAGER - REGULATORY AFFAIRS (419-321-8450) AT THE DBNPS OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

COMMITMENTS DUE DATE The requirements for maintaining a hydrogen Concurrent with monitoring system capable of diagnosing beyond implementation of the design-basis accidents as described above will be associated license included in the DBNPS USAR Technical Requirements amendment.

Manual.

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