ML043630376

Application for Amendment Regarding the Revision to Diesel Fuel Oil Requirements

ML043630376
Person / Time
Site:	Ginna
Issue date:	12/20/2004
From:	Korsnick M Constellation Energy Group
To:	Clark R Document Control Desk, Office of Nuclear Reactor Regulation
References
NUREG-1431
Download: ML043630376 (22)

Text

Maria Korsnick 1503 Lake Road Vice President Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria.korsnick~constellation.com Constellation Energy R.E. Ginna Nuclear Power Plant December 20, 2004 Mr. Robert L. Clark Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Application for Amendment to Facility Operating License Revision to Diesel Fuel Oil Requirements R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Clark:

In accordance with the provisions of 10 CFR 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC) is submitting a request for an amendment to the Technical Specifications (TS) for the R.E. Ginna Nuclear Power Plant.

The proposed amendment would make three changes in the surveillance requirements to establish and verify the acceptability of new diesel fuel oil for use, prior to addition to storage tanks, and to stored fuel oil. (1) The existing requirement to perform a "clear and bright" surveillance would be revised to include the option to perform a test for water and sediment in lieu of the "clear and bright" test, (2) a requirement to perform a surveillance, and the associated acceptance criteria, for particulate limit for stored diesel fuel oil would be added, and (3) the invoking of the standard surveillance test frequency exception would be added. The changes are consistent with NRC approved Revision 3 to NUREG-1431, Standard Technical Specifications Westinghouse Plants.

Enclosure I provides a description and assessment of the proposed changes. Enclosure 2 provides the existing TS pages marked up to show the proposed changes. Enclosure 3 provides revised (clean) TS pages. There are no additional commitments associated with this amendment request.

Ginna LLC requests approval of the proposed license amendment by July 1, 2005 with the amendment being implemented within 90 days.

I DO RId-

In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to the designated New York State Official.

Any questions concerning this submittal should be directed to Thomas Harding, Nuclear Safety and Licensing at (585) 771-3384.

ayyXerytrulyoj~~.rs] /

Mary Korsnick

Enclosures:

1. Description and Assessment

2. Proposed Technical Specification Changes (markup)

3. Revised Technical Specification Pages STATE OF NEW YORK:

TO WIT:

COUNTY OF WAYNE :

I, Mary G. Korsnick, being duly sworn, state that I am Vice President - R.E. Ginna Nuclear Power Plant, LLC (Ginna LLC), and that I am duly authorized to execute and file this response on behalf of Ginna LLC. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other Ginna LLC employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

Subscribed and sworn before me, a Notary Publiq in and for the State of New York and County of MoN pRa ,this O day of f 2004.

WITNESS my Hand and Notarial Seal:

Notary Public SHARON L MILLER N* NWy Pia odNowYoft My Commission Expires: 1qggw No.OlMI1617756 COEwD21,_,Q

/ e0 (o Date

xc: Mr. Robert L. Clark (Mail Stop 0-8-C2)

Project Directorate I Division of Licensing Project Management Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector James M. Petro Jr., Esquire Counsel Constellation Energy 750 East Pratt Street, 5th Floor Baltimore, MD 21202 Mr. Peter R. Smith New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul D. Eddy Electric Division NYS Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223

Enclosure I R.E. Ginna Nuclear Power Plant Description and Assessment

Subject:

Diesel Fuel Oil Requirements in Specification 5.5.12

4.0 TECHNICAL ANALYSIS

5.0 NO SIGNIFICANT HAZARDS CONSIDERATION

1.0 DESCRIPTION

This proposed change to the Ginna Station Technical Specifications (TS) provides for consistency with the testing requirements for new and stored diesel fuel oil as provided in Revision 3 to NUREG-1431, Standard Technical Specifications Westinghouse Plants.

2.0 PROPOSED CHANGE

The proposed changes revise TS 5.5.12, Diesel Fuel Oil Testing Program as follows.

• TS 5.5.12.a.2 currently states "a clear and bright appearance with proper color,"

TS 5.5.12.a.2 has been revised to state "a clear and bright appearance with proper color or a water and sediment content within limits,"

• TS 5.5.12 does not currently include a stored fuel oil requirement to test for particulate contamination TS 5.5.12.c has been added which states, "Total particulate concentration of the fuel oil is

• 10 mgfl when tested every 92 days."

• TS 5.5.12 does not currently include a discussion of surveillance exceptions TS 5.5.12 has been revised to add "The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program surveillance frequencies."

3.0 BACKGROUND

The diesel fuel oil testing is a means of determining whether new and stored fuel oil is of the appropriate grade (i.e., proper fuel oil quality) and of assuring that it has not been contaminated with substances that would have an immediate, detrimental impact on diesel engine combustion.

The "clear and bright appearance with proper color" test is one of the tests used to establish the acceptability of new fuel oil for use prior to addition to storage tanks. This requirement has been expanded to allow the option of a water and sediment content test to be performed to establish the acceptability of new fuel oil. The "clear and bright" test is a qualitative test for determining free water and contamination in distillate fuels and is, therefore, subject to human interpretation. For example, if an attempt is made to use the qualitative "clear and bright" test with darker colored fuels (e.g., for high sulfur fuel oil that has been dyed in accordance with EPA mandated requirements), the presence of free water or contaminants could be obscured and missed by the viewer. Therefore, Specification 5.5.12.a.2 has been expanded to allow the option of a water and sediment content test.

The addition of the requirement to test for particulate contamination for stored fuel and the addition of SR 3.0.2 and SR 3.0.3 provide further consistency with the standard technical specifications and industry practice.

4.0 TECHNICAL ANALYSIS

The initial conditions of Design Basis Accident (DBA) and transient analyses assume Engineered Safety Feature (ESF) systems are OPERABLE. The diesel generators (DGs) are designed to provide sufficient capacity, capability, redundancy, and reliability to ensure the availability of necessary power to ESF systems so that fuel, Reactor Coolant System, and containment design limits are not exceeded. For proper operation of the DGs, it is necessary to ensure the proper quality of the fuel oil.

The water and sediment content test is a quantitative test using centrifuge methods.

ASTM D2709, "Test Method for Water and Sediment in Distillate Fuels by Centrifuge,"

or ASTM D1796, "Standard Method for Water and Sediment in Fuel Oils by the Centrifuge Method (Laboratory Procedure)," are acceptable standards for the water and sediment content test. This testing is currently performed within 31 days following addition to the storage tanks as required by TS 5.5.12.b. Therefore, since ASTM D2709 or ASTM D1796 are currently used to verify the acceptability of new fuel oil for use following addition to the storage tanks, the use of these quantitative methods (i.e., water and sediment content) in lieu of ASTM D4176 (i.e., "clear and bright" test) does not introduce a different method that requires further evaluation prior to implementation.

The addition of the test for total particulate concentration of the stored fuel oil is consistent with the intent of the testing program and provides assurance of the long term storage quality of the fuel, of which degradation could lead to engine failure. The modified ASTM D2276 test is an acceptable method to determine particulate concentrations in stored fuel oil. The acceptance criteria of 10 mg/i particulate is consistent with standard technical specifications. The proposed frequency of 92 days is consistent with the current stored fuel oil surveillance program as described in the Bases of SR 3.8.3.2, and is consistent with the frequency approved for the Millstone Power Station, Unit No. 2 (Ref. 7.1).

The addition of the SR 3.0.2 and SR 3.0.3 provisions to the Diesel Fuel Oil Testing Program provide consistency with the Surveillance Requirements which reference this program and standard technical specifications. The addition of these provisions are also consistent with other Administrative Control Programs, such as 5.5.6, "Pre-Stressed Concrete Containment Tendon Surveillance Program," and in 5.5.10, "Ventilation Filter Testing Program."

The proposed TS changes will continue to provide reasonable assurance of the quality of both new fuel oil and stored fuel oil designated for use in the DGs. Therefore, the OPERABILITY of the DGs is unaffected.

5.0 NO SIGNIFICANT HAZARDS DETERMINATION Ginna LLC has evaluated 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 changes involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed changes involve the expansion of the test used to establish the acceptability of new fuel oil for use prior to addition to storage tanks, to allow a water and sediment content test to be performed. In addition, a limit is being added for the amount of particulate allowed in stored fuel, and the specific allowance to utilize the exceptions of SR 3.0.2 and SR 3.0.3.

Allowing a water and sediment content test to be performed to establish the acceptability of new fuel oil, including a limit for particulate for the stored fuel oil, and adding the allowance of SR 3.0.2 and SR 3.0.3 will not affect nor degrade the ability of the emergency diesel generators (DGs) to perform their specified safety function.

The proposed changes do not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, and configuration of the facility or the manner in which the plant is operated and maintained. The proposed changes do not alter or prevent the ability of structures, systems, and components (SSCs) from performing their intended function to mitigate the consequences of an initiating event within the assumed acceptance limits. The proposed changes do not affect the source term, containment isolation, or radiological release assumptions used in evaluating the radiological consequences of an accident previously evaluated. Further, the proposed changes do not increase the types and amounts of radioactive effluent that may be released offsite, nor significantly increase individual or cumulative occupational/public radiation exposures.

Therefore, the changes do not involve a significant increase in the probability or consequences of an 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 proposed changes involve the expansion of the test used to establish the acceptability of new fuel oil for use prior to addition to the storage tanks, to allow a water and sediment content test to be performed. In addition, a limit is being added for the amount of particulate allowed in stored fuel, and the specific allowance to utilize the exceptions of SR 3.0.2 and SR 3.0.3.

The changes do not involve a physical alteration of the plant (i.e., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation. The changes do not alter assumptions made in the safety analysis and licensing basis.

Therefore, the changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

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

Response: No The proposed changes involve the expansion of the test used to establish the acceptability of new fuel oil for use prior to addition to storage tanks, to allow a water and sediment content test to be performed. In addition, a limit is being added for the amount of particulate allowed in stored fuel, and the specific allowance to utilize the exceptions of SR 3.0.2 and SR 3.0.3.

The level of safety of facility operation is unaffected by the proposed changes since there is no change in the intent of the TS requirements of assuring fuel oil is of the appropriate quality for emergency DG use. The response of the plant systems to accidents and transients reported in the Updated Final Safety Analysis Report (UFSAR) is unaffected by this change. Therefore, accident analysis acceptance criteria are not affected.

The proposed changes do not reduce a margin of safety since they have no impact on any transient or safety analysis assumptions. Therefore, the changes do not involve a significant reduction in a margin of safety.

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

6.0 ENVIRONMENTAL EVALUATION Ginna LLC has evaluated the proposed changes and determined that:

1. The changes do not involve a significant hazards consideration; and

2. The changes do not involve a significant change in the types or significant increase in the amounts of any effluent that may be released offsite since there is no change in accident assumptions; and

3. The changes do not involve a significant increase in individual or cumulative occupational radiation exposure since no new or different type of equipment are required to be installed as a result of this LAR.

Accordingly, the proposed changes meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed changes is not required.

Nuclear

7.0 REFERENCES

to David A. Christian (Dominion NO. 2 -

B. Ennis (NRC) UNIT 7.1 Letter from Richard"MILLSTONE POWER STATION,DIESEL GENERATOR Connecticut, Inc.), RE: EMERGENCY AMENDMENTACCESSION NUMBER: ML031640541, ISSUANCE OF TESTING REQUIREMENTS",

July 25, 2003.

Enclosure 2 R.E. Ginna Nuclear Power Plant Proposed Technical Specification Changes (markup)

Programs and Manuals 5.5

2. a flash point and kinematic viscosity within limits for ASTM 2D 2 fuel oil, and {6-wn SJ 2 S<e .a* ',od 4 J. 8 days in gaseous effluents released from the plant to areas beyond the site boundary, conforming to 10 CFR 50, Appendix l; and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 Component Cyclic or Transient Limit Proaram This program provides controls to track the reactor coolant system cyclic and transient occurrences specified in UFSAR Table 5.1-4 to ensure that components are maintained within the design limits.

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance P rogram This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity.

The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Regulatory Guide 1.35, Revision 2.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

R.E. Ginna Nuclear Power Plant 5.5-3 Amendment

Programs and Manuals 5.5 5.5.7 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports. The program shall include the following:

a. Testing frequencies specified in Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and Required Frenuencies for applicable Addenda termnhology for Inservice performing Inservice testing testina actvities activties Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

5.5.8 Steam Generator (SG) Tube Surveillance Proaram Each SG shall be demonstrated OPERABLE by performance of an inservice inspection program in accordance with the Nuclear Policy Manual. This inspection program shall define the specific requirements of the edition and Addenda of the ASME Boiler and Pressure Code, Section Xl, as required by 10 CFR 50.55a(g). The program shall include the following:

a. The inspection intervals for SG tubes shall be specified in the Inservice Inspection Program.

R.E. Ginna Nuclear Power Plant 5.5-4 Amendment

Programs and Manuals 5.5

b. SG tubes that have imperfections > 40% through wall, as indicated by eddy current, shall be repaired by plugging or sleeving.

c. SG sleeves that have imperfections > 30% through wall, as indicated by eddy current, shall be repaired by plugging.

5.5.9 Secondary Water Chemistry Program This program provides controls for monitoring secondary water chemistry to inhibitS G tubex egradation. This program shall include:

a. Identification of a sampling schedule for the critical variables and control points for these variables;

b. Identification of the procedures used to measure the values of the critical variables;

c. Identification of process sampling points;

d. Procedures for the recording and management of data;

e. Procedures defining corrective actions for all off control point chemistry conditions; and

f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.

5.5.10 Ventilation Filter Testing Program (VXEIP)

A program shall be established to implement the following required testing of Engineered Safety Feature filter ventilation systems and the Spent Fuel Pool (SFP) Charcoal Adsorber System. The test frequencies will be in accordance with Regulatory Guide 1.52, Revision 2, except that in lieu of 18 month test intervals, a 24 month interval will be implemented.

The test methods will be in accordance with Regulatory Guide 1.52, Revision 2, except as modified below.

a. Containment Post-Accident Charcoal System

1. Demonstrate the pressure drop across the charcoal adsorber bank is < 3 inches of water at a design flow rate (+/- 10%).

2. Demonstrate that an in-place Freon test of the charcoal adsorber bank shows a penetration and system bypass

< 1.0%, when tested under ambient conditions.

R.E. Ginna Nuclear Power Plant 5.5-5 Amendment

Programs and Manuals 5.5

3. Demonstrate that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows a methyl iodide penetration of less than 14.5% when tested in accord ance with ASTM D3803-1989 at a test temperature of 301C (86IF) and a relative humidity of 95%.

b. Containment Recirculation Fan Cooler System

1. Demonstrate the pressure drop across the high efficiency particulate air (HEPA) filter bank is < 3inches of water at a design flow rate (+/- 10%).

2. Demonstrate that an in-place dioctylphthalate (DOP ) test of the HEPA filter bank shows a penetration and system bypass

< 1.0%.

c. Control Room Emergency Air Treatment System (CREATS)

1. Demonstrate the pressure drop across the HEPA filter bank is

< 3 inches of water at a design flow rate (+/- 10%).

2. Demonstrate that an in-place DOP test of the HE PA filter bank shows a penetration and system bypass < 1.0%.

3. Demonstrate the pressure drop across the charcoal adsorber bank is < 3 inches of water at a design flow rate (+/- 10%).

4. Demonstrate that an in-place Freon test of the charcoal adsorber bank shows a penetration and system bypass

< 1.0%, when tested under ambient conditions.

5. Demonstrate that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows a methyl iodide penetration of less than 14.5% when tested in accord ance with ASTM D3803-1989 at a test temperature of 30 0C (860F) and a relative humidity of 95%.

d. SFP Charcoal Adsorber System

1. Demonstrate that the total air flow rate from the charcoal adsorbers shows at least 75% of that measured with a complete set of new adsorbers.

2. Demonstrate that an in-place Freon test of the charcoal adsorbers bank shows a penetration and system bypass

< 1.0%, when tested under ambient conditions.

R.E. Ginna Nuclear Power Plant 5.5-6 Amendment

Programs and Manuals 5.5

3. Demonstrate that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows a methyl iodide penetration of less than 14.5% when tested in accord ance with ASTM D3803-1989 at a test temperature of 30 0 C (86 0F) and a relative humidity of 95%.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP frequencies.

5.5.11 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the waste gas decay tanks and the quantity of radioactivity contained in waste gas decay-tanks: The gaseous radioactivity quantities shall be determined following the methodology in NU REG-0133.

The program shall include:

a. The limits for concentrations of hydrog en and oxygen in the waste gas decay tanks and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion); and

b. A surveillance program to ensure that the quantity of radioactivity contained in each waste gas decay tank is less than the amount that would result in a whole body exposure of 2 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.

5.5.12 Diesel Fuel Oil Testing Program A diesel fuel oil testinig program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. an API gravity or an absolute specific gravity within lim its, R.E. Ginna Nuclear Power Plant 5.5-7 Amendment

Programs and Manuals 5.5

2. aflash point and kinematic viscosity within limits for ASTM 2D.

fuel oil, and

3. a clear and bright appearance with proper color or a water and sediment content within limits; and

b. Within 31 days following addition of the new fuel to the sto rage tanks, verify that the properties of the new fuel oil, other than those addressed in a. above, are within limits for ASTM 2D fuel oil; and

c. Total particulate concentration of the fuel oil is s 10 mg/l when tested every 92 days.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test frequencies.

5.5.13 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.

d. Proposed changes that meet the criteria of Specification 5.5.13.b.1 or Specification 5.5.13.b.2 shall be reviewed and approved by the NRC priorto implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71e.

5.5.14 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and R.E. Ginna Nuclear Power Plant 5.5-8 Amendment.

Programs and Manuals 5.5 Required Actions. This program implements the requirements of LCO 3.0.6. The SFDP shall contain the following-

a. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

--d.-Other-appropriate limitations -and remedial or compensatory

' actions.- -. -.

A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to the supported system(s) is also inoperable; or

b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or

c. A required system redundant to the inoperable support system(s) for the supported systems (a)and (b) above is also inoperable.

The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

5.5.15 Containment Leakage Rate Testing Procram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines cont ained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa. is 60 psig.

R.E. Ginna Nuclear Power Plant 5.5-9 Amendment

Programs and Manuals 5.5 The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.2% of containment air weight ber day.

Leakage Rate acceptance criteria are:

a. Containment leakage rate acceptance criterion is s 1.0 La. During the first plant startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the Type B and Type C tests and

• 0.75 La for Type A tests;

b. Air lock testing acceptance criteria are:

1. For each air lock, overall leakage rate is

• 0.05 La when

_F- Ž,tested

, atŽ Z.a, and-_...

2. For each door, leakage rate is 50.01 La when tested at 2 Pa.

c. Mini-purge valve acceptance criteria is

• 0.05 La when tested at 2 Pa.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

The provisions of SR 3.0.3 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.

R.E. Ginna Nuclear Power Plant 5.5-1 0 Amendment