HNP-99-083, Application for Amend to License NPF-63,revising TS to Incorporate performance-based 10CFR50 App J,Option B for Type a Tests (Containment Integrated Leakage Rate Tests)
| ML18016A989 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/15/1999 |
| From: | Scarola J CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18016A990 | List: |
| References | |
| HNP-99-083, HNP-99-83, NUDOCS 9906220205 | |
| Download: ML18016A989 (13) | |
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CATEGORY 1
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9906220205 DOC.DATE: 99/06/15 NOTARIZED: YES FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina
.AUTH"NAME AUTHOR AFFILIATION SCAROLA,J.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)
DOCKET 05000400
SUBJECT:
Application for amend to license NPF-63,revising TS to incorporate performance-based 10CFR50 App J,Option B for Type A tests (containment integrated leakage rate tests).
DISTRIBUTION CODE: A017D COPIES RECEIVED:LTR i ENCL J SIZE: /6 TITLE: OR Submittal:
Append J Containment Leak Rate Testing NOTES:Application for permit renewal filed.
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N NOTE TO ALL "RIDS" RECIPIENTS:
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Carolina Power &light Company PO Box 165 New Hill NC 27562 James Scarola Vice President Harris Nuclear Plant JUN 1 5 1999 SERIAL: HNP-99-083 10 CFR 50.90 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEARPOWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CONTAINMENTINTEGRATEDLEAKAGERATE TESTING
Dear Sir or Madam:
In accordance with the Code ofFederal Regulations, Title 10, Part 50.90, Carolina Power 8c Light Company (CPS') requests a revision to the Technical Specifications (TS) for the Harris Nuclear Plant (HNP). The proposed amendment revises the TS to incorporate the performance-based 10 CFR 50 Appendix J, Option B for Type A tests (containment integrated leakage rate tests). Option B willbe implemented for Type A testing in accordance with NRC Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, and Nuclear Energy Institute (NEI) Guideline 94-01, Revision 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," dated July 26, 1995.
Type B and C testing (containment penetration leakage tests) willcontinue to be performed in accordance with 10 CFR 50 Appendix J, Option A.
Enclosure 1 provides a description of the proposed changes and the basis for the changes. details, in accordance with 10 CFR 50.91(a), the basis for CPEcL's determination that the proposed changes do not involve a significant hazards consideration. provides an environmental evaluation which demonstrates that the proposed amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental assessment is required for approval of this amendment request. provides page change instructions for incorporating the proposed revisions. provides the proposed TS pages.
9906220205 9906%5 PDR ADDCK 05000400 P
PDR I
5413 Shearon Harris Road New Hill,NC Tel 919 362-2502 Fax 919 362-2095
Document Control Desk SERIAL: HNP-99-083 Page 2 CP&L requests approval of the proposed amendment by November 15, 1999 to support planning for HNP Refueling Outage 9, currently scheduled to begin in April2000. CP&L also requests that the proposed amendment be issued such that implementation willoccur within 60 days of issuance to allow time for orderly incorporation into copies of the TS.
Please refer any questions regarding this submittal to Mr. J. H. Eads at (919) 362-2646.
Sincerely, AEC
Enclosures:
- 1. Basis for Change Request
- 2. 10 CFR 50.92 Evaluation
- 3. Environmental Considerations
- 4. Page Change Instructions
- 5. Technical Specification Pages James Scarola, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are employees, contractors, and agents of Carolina Power &Light Company.
My commission expires: g-4, CC:
Mr. J. B. Brady, NRC Sr. Resident Inspector Mr. Mel Fry, Director, N.C. DEHNR Mr. R. J. Laufer, NRC Project Manager Mr. L. A. Reyes, NRC Regional Administrator J
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Enclosure 1 to SERIALHNP-99-083 Page1of 4 SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CONTAINMENTINTEGRATEDLEAKAGERATE TESTING BASIS FOR CHANGE RE UEST
~Back round The containment structure provides biological shielding and missile protection for the Nuclear Steam Supply System and is designed to withstand the pressure and temperature transient calculated to exist after a design basis accident. The containment structure and the engineered safety features ensure that the radiological exposure to the public resulting from a design basis accident is below the guidelines established in 10 CFR 100. <<The capability of the containment structure to maintain design leaktight integrity and to provide a predictable environment for operation of engineered safety features systems is ensured by design, analysis and testing..
Compliance with 10 CFR 50 Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," provides assurance that the primary containment, including those systems and components which penetrate the primary containment, does not exceed the allowable leakage rate specified in the Technical Specifications (TS) and Bases.
On February 4, 1992, the Nuclear Regulatory Commission (NRC) published a notice in the Federal Register (57 FR 4166) discussing a planned initiative to begin eliminating requirements marginal to safety which impose a significant regulatory burden. Appendix J of 10 CFR 50 was considered for this initiative and the NRC staff undertook a study of possible changes to this regulation. The study examined the previous performance history of domestic reactor plant containments and evaluated the effect on risk of a revision to the requirements of Appendix J.
The results of this study are reported in NUREG-1493, "Performance-Based Containment Leak-Test Program," published September 1995.
On July 26, 1995, Nuclear Energy Institute (NEI) guidance document NEI 94-01, Revision 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," was published to provide consistent guidance for implementing a performance-based containment leakage testing program.
On September 26, 1995, the NRC published a final rule regarding primary reactor containment leakage testing for water-cooled power reactors (60 FR 49495). The new rule amended 10 CFR Part 50 Appendix J, by adding Option B, "Performance-Based Requirements."
Option B allows licensees to voluntarily replace Appendix J, Option A, "Prescriptive Requirements," with testing requirements based on both overall and individual component leakage rate performance.
NRC Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Test Program," was also published in September 1995, as a method acceptable to the NRC staff for complying with the performance-based Appendix J, Option B. RG 1.163 provides four exceptions to the guidance in NEI 94-01, Revision 0. Exception 1 discusses the test interval for Type A tests. The RG states that ANSVANS 56.8-1994, "Containment System Leakage Testing Requirements,"
test intervals are not performance-based.
Therefore, licensees intending to comply with 10 CFR
Enclosure 1 to SERIALHNP-99-083 Page2of 4 Part 50 Appendix J, Option B for Type A test intervals must comply with Section 11.0 ofNEI 94-01.
Section 11.0 of NEI 94-01 refers the licensee to Sections 9 and 10 of that document.
Section 9.2.3 "Extended Test Intervals," discusses Type A tests. This section states that Type A testing shall be performed during a period of reactor shutdown at a frequency of at least once per 10 years based on acceptable, performance history. Acceptable performance history is defined as completion of two consecutive period Type A tests where the calculated performance leakage rate was less than 1.0L,. Elapsed time between the first and last tests in a series shall be at least 24 months.
Exception 3 discusses the visual examination of accessible internal and exterior surfaces of the containment system for structural problems.
Exception 3 further states "These examinations should be conducted prior to initiating a Type A test, and during two other refueling outages before the next Type A test ifthe interval for the Type A test'has been extended to 10 years, in order to allow for early uncovering of evidence of structural deterioration."
The other two exceptions in RG 1.163 are not pertinent to the discussion ofType A test frequencies, but instead involve Type B and C testing, which is not part of this license amendment request.
Pro osed Chan es Technical Specification (TS) 6.8.4.k, "Containment Leakage Rate Testing Program" willbe added to the "Procedures and Programs" section of the Harris Nuclear Plant (HNP) TS. The Containment Leakage Rate Testing 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 NRC Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program" with the exception that the Containment Leakage Rate Testing Program is only applicable to Type A testing. Type B and C testing shall continue to be conducted in accordance with the original commitment to 10 CFR 50 Appendix J, Option A. In addition, TS 6.8.4.k specifies that the peak containment internal pressure, Pwillbe conservatively assumed to be 41.2 psig. The maximum allowable containment leakage rate, L, at Pshall be 0.1% of containment air weight per day. The containment overall leakage rate acceptance criterion is ( 1.0 I
. During the first unit startup followingtesting in accordance with this program, the leakage. rate acceptance criteria are ( 0.60 I for the combined Type B and Type C tests, and (0.75 I for Type A tests. The provisions of Surveillance Requirement (SR) 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
Test frequencies may be extended consistent with the guidance provided in NEI 94-01. The provisions of SR 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
The "Containment Leakage" LimitingCondition for Operation (LCO) 3.6.1.2 willbe revised to reflect that the overall integrated leakage rate shall be limited to the limits specified in the Containment Leakage Rate Testing Program (TS 6.8.4.k).
SR 4.6.1.2 willbe revised by replacing the introductory paragraph and 4.6.1.2.a, 4.6.1.2.b and 4.6.1.2.c with the following: "The containment leakage rate Type A tests shall be performed in
7 Enclosure 1 to SERIALHN 083 Page 3 of 4 accordance with the Containment Leakage Rate Testing Program (TS 6.8.4.k). The containment leakage rate Type B and C tests shall be demonstrated at the test schedule and shall be determined in accordance with the criteria specified in 10 CFR Part 50 Appendix J, Option A."
The Basis for TS 3/4.6.1.2 willbe revised to clarify that the surveillance testing for measuring leakage rates is consistent with the requirements of 10 CFR 50 Appendix J, Option A for Type B and C tests, and the Containment Leakage Rate Testing Program (TS 6.8.4.k) for Type A tests.
Also, the sentence referring to a one time extension of the test interval willbe deleted from this Basis.
The "Containment Integrity" SR 4.6.1.1.c and the "Containment AirLocks" SR 4.6.1.3.a willbe revised to delete the "41 psig" specification of P,. (P, willbe specified in TS 6.8.4.k, "Containment Leakage Rate Testing Program.")
The "Containment Vessel Structural Integrity" SR 4.6.1.6.1 willbe revised to stipulate that "Additional inspections shall be conducted during two other refueling outages before the next Type A test ifthe interval for the Type A test has been extended to 10 years." The Basis forTS 3/4.6.1.6 willbe revised to indicate that a visual inspection in conjunction with the Containment Leakage Rate Testing Program is sufficient to demonstrate the containment structural integrity.
Basis The purpose of conducting Type A, containment integrated leakage rate tests (ILRTs), is to verify the leakage integrity of the containment structure. The Type A testing methodology described in ANSI/ANS 56.8-1994 and the modified testing frequencies described in 10 CFR 50 Appendix J, Option B ensure leakage integrity of the containment structure. The specific requirements of Appendix J, Option B include completion of one Type A test during reactor shutdown at least once every 10 years.
The extended Type A test interval is based upon industry performance data compiled to support the development of Option B to Appendix J, as documented in NUREG-1493. NUREG-1493, Section 10.1.2, "Leakage-Testing Intervals," states the followingfor Type A testing:
"1. Reducing the frequency ofType A tests (ILRTs) from the current three per 10 years to one per 20 years was found to lead to an imperceptible increase in risk.
The estimated increase in risk is very small because ILRTs identify only a few potential containment leakage paths that cannot be identified by Type B and C testing, and the leaks that have been found by Type A tests have been only marginally above existing requirements."
"2. Given the insensitivity of the risk to containment leakage rate and the small fraction of leakage paths detected solely by Type A testing, increasing the interval between integrated leakage-rate tests is possible with minimal impact on public risk."
HNP's application of this test interval is based on acceptable performance history. The pre-operational Type A test for the HNP containment structure was successfully performed in February 1986. Two consecutive periodic Type A tests have been satisfactorily completed at
Enclosure 1 to SERIALHNP-99-083 Page4of 4 HNP, the first in September 1992 and the second in May 1997. The September 1992 test results w'ere documented by General Physics Corporation in the "Reactor Containment Building Integrated Leakage Rate Test Report," dated October 13, 1992, and subsequently reported to the NRC by letter dated January 12, 1993. The May 1997 test results were documented by General Physics Corporation in the "Reactor Containment Building Integrated Leakage Rate Test Report," dated August 26, 1997. With these two successful Type A tests, and a greater than 24 month elapsed time between the two tests, CP&Lconsiders the requirement oftwo consecutive Type A tests to have been met and application of the test interval of once every 10 years to be appropriate.
10.CFR 50 Appendix J requires that for adoption of Option B, licensees are required to incorporate into their Technical Specifications, by general reference, the NRC Regulatory Guide or other plant-specific implementing document. A new Administrative Control Subsection, 6.8.4.k, is being added to the HNP TS that requires the establishment and maintenance of a Containment Leakage Rate Testing Program.
As stated in the revised TS, this Containment Leakage Rate Testing Program willconform with NRC Regulatory Guide 1.163, Revision 0, dated September 1995, "Performance-Based Containment Leak-Rate Test Program," by establishing Type A leakage testing intervals based on the criteria in Section 11.0 ofNEI 94-01, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J." The TS willcontinue to require performance of a general visual inspection of the containment prior to Type A testing to ensure early detection of any structural deterioration of the containment system that might occur. Additionally, the revised TS require a periodic general visual inspection to be conducted during two other refueling outages before the next Type A test ifthe interval has been extended to 10 years.
to SERIALHN 083 Page1of 3
SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR Ll;CENSE AMENDMENT CONTAINMENTINTEGRATEDLEAKAGERATETESTING 10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facilityinvolves no significant hazards consideration ifoperation of the facilityin accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. Carolina Power Ec Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards determination.
The basis for this determination is provided below.
Pro osed Chan es Technical Specification (TS) 6.8.4.k, "Containment Leakage Rate Testing Program" willbe added to the "Procedures and Programs" section of the Harris Nuclear Plant (HNP) TS. The Containment Leakage Rate Testing 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 NRC Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program" with the exception that the Containment Leakage Rate Testing Program is only applicable to Type A testing. Type B and C testing shall continue to be conducted in accordance with the original commitment to 10 CFR 50 Appendix J, Option A. In addition, TS 6.8.4.k specifies that the peak containment internal pressure, Pwillbe conservatively assumed to be 41.2 psig. The maximum allowable containment leakage rate, L, at Pshall be 0.1% of containment air weight per day. The containment overall leakage rate acceptance criterion is ( 1.0 L,. During the first unit startup followingtesting in accordance with this program, the leakage rate acceptance criteria are (0.60 I for the combined Type B and Type C tests, and (0.75 L, for Type A tests. The provisions of Surveillance Requirement (SR) 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program.
Test frequencies may be extended consistent with the guidance provided in NEI 94-01. The provisions of SR 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
The "Containment Leakage" LimitingCondition for Operation (LCO) 3.6.1.2 willbe revised to reflect that the overall integrated leakage rate shall be limited'to the limits specified in the Containment Leakage Rate Testing Program (TS 6.8.4.k).
SR 4.6.1.2 willbe revised by replacing the introductory paragraph and 4.6.1.2.a, 4.6.1.2.b and 4.6.1.2.c with the following: "The containment leakage rate Type A tests shall be performed in accordance with the Containment Leakage Rate Testing Program (TS 6.8.4.k). The containment leakage rate Type B and C tests shall be demonstrated at the test schedule and shall be determined in accordance with the criteria specified in 10, CFR Part 50 Appendix J, Option A."
to SERIAL 083 Page2of 3
The Basis for TS 3/4.6.1.2 willbe revised to clarify that the surveillance testing for measuring leakage rates is consistent with the requirements of 10 CFR 50 Appendix J, Option A for Type B and C tests, and the Containment Leakage Rate Testing Program (TS 6.8.4.k) for Type A tests.
Also, the sentence referring to a one time extension of the test interval willbe deleted from this Basis.
The "Containment Integrity" SR 4.6.1.1.c and the "Containment AirLocks" SR 4.6.1.3.a willbe revised to delete the "41 psig" specification of P,. (P, willbe specified in TS 6.8.4.k, "Containment Leakage Rate Testing Program.")
The "Containment Vessel Structural Integrity" SR 4.6.1.6.1 willbe revised to stipulate that "Additional inspections shall be conducted during two other refueling outages before the next Type A test ifthe interval for the Type A test has been extended to 10 years." The Basis for TS 3/4.6.1.6 willbe revised to indicate that a visual inspection in conjunction with the Containment Leakage Rate Testing Program is sufficient to demonstrate the containment structural integrity.
Basis The changes do not involve a significant hazards consideration for the followingreasons:
The proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The Harris Nuclear Plant (HNP) Type A testing history provides justification for the proposed test schedule change to one test in a 10 year period. With the successful Type A tests of September 1992 and May 1997, and a greater than 24 month elapsed time between the two tests, CP8cL considers the requirement of two consecutive Type A tests to have been met. This testing has affirmed the acceptable reliabilityof the containment structure to minimize leakage as designed, and provides assurance that its performance to continuously function as designed is not challenged due to this test schedule extension to once in 10 years.
This proposed change to revise the test schedule frequency does not impact or alter the design of any system, structure or component.
The limiton allowable leakage is not increased.
Type A testing provides periodic verification of the leak tight integrity of the containment and the components that penetrate the containment structure. NUREG-1493, Section 10.1.2, "Leakage-Testing Intervals," states that reducing the frequency of Type A tests from the current three per 10 years to one per 20 years was found to lead to an imperceptible increase in risk.
Therefore, based on these considerations, and the previous plant-specific Type A test results, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
to SERIALHN 083 Page 3 of 3 2.'he proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes only incorporate the performance-based testing approach authorized in 10 CFR 50 Appendix J, Option B, and are justified based on previous plant-specific Type A test results.
Plant structures, systems, and components willnot be operated in a different manner as a result of these proposed changes and no physical modifications to equipment are involved. The interval extensions allowed by Option B of 10 CFR 50 Appendix J do not have the potential for creating the possibility of a new or different type of accident from any previously evaluated.
3.
The proposed amendment does not involve a significant reduction in the margin of safety.
The proposed changes do not change the allowable leak rate from the containment; they only allow an extension of the interval between the performance ofType A leak rate testing. NUREG-1493 provides the technical basis for the NRC's rulemaking to revise containment leakage testing requirements for nuclear power reactors in 10 CFR 50 Appendix J. NUREG-1493, Section 10.1.2, "Leakage-Testing Intervals," states that increasing the interval between integrated leakage-rate tests is possible with minimal impact on public risk.
Based on these considerations and the previous plant-specific Type A test results, the proposed changes do not involve a reduction in the margin of safety.
Conclusion Based on the above evaluation, it is concluded that the proposed amendment does not involve a significant hazards consideration.
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SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CONTAINMENTINTEGRATEDLEAKAGERATE TESTING ENVIRONMENTALCONSIDERATIONS I
10 CFR 51.22(c)(9) provides criteria for licensing and regulatory actions eligible for categorical exclusion from performing an environmental assessment.
A proposed amendment to an operating license for a facilityrequires no environmental assessment ifoperation of the facilityin accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite; (3) result in a significant increase in individual or cumulative occupational radiation exposure.
Carolina Power'Ec Light Company has reviewed this request and determined that the proposed amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment.
The basis for this determination is provided below.
Pro osedChan es Technical Specification (TS) 6.8.4.k, "Containment Leakage Rate Testing Program" willbe added to the "Procedures and Programs" section of the Harris Nuclear Plant (HNP) TS. The Containment Leakage Rate Testing 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 NRC Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program" with the exception that the Containment Leakage Rate Testing Program is only applicable to Type A testing. Type B and C testing shall continue to be conducted in accordance with the original commitment to 10 CFR 50 Appendix J, Option A. In addition, TS 6.8.4.k specifies that the peak containment internal pressure, Pwillbe conservatively assumed to be 41.2 psig. The maximum allowable containment leakage rate, L, at Pshall be 0.1% of containment air weight per day. The containment overall leakage rate acceptance criterion is < 1.0 L,. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 L, for the combined Type B and Type C tests, and < 0.75 I for Type A tests. The provisions of Surveillance Requirement (SR) 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program. Test frequencies may be extended consistent with the guidance provided in NEI 94-01. The provisions of SR 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
The "Containment Leakage" LimitingCondition for Operation (LCO) 3.6.1.2 willbe revised to reflect that the overall integrated leakage rate shall be limited to the limits specified in the Containment Leakage Rate Testing Program (TS 6.8.4.k).
SR 4.6.1.2 willbe revised by replacing the introductory paragraph and 4.6.1.2.a, 4.6.1.2.b and 4.6.1.2.c with the following: "The containment leakage rate Type A tests shall be performed in accordance with the Containment Leakage Rate Testing Program (TS 6.8.4.k). The containment to SERIAL 083 Page2of 2
leakage rate Type B and C tests shall be demonstrated at the test schedule and shall be determined iri accordance with the criteria specified in 10 CFR Part 50 Appendix J, Option A."
The Basis for TS 3/4.6.1.2 willbe revised to clarify that the surveillance testing for measuring leakage rates is consistent with the requirements of 10 CFR 50 Appendix J, Option A for Type B and C tests, and the Containment Leakage Rate Testing Program (TS 6.8.4.k) for Type A tests.
Also, the sentence referring to a one time extension of the test interval willbe deleted from this Basis.
The "Containment Integrity" SR 4.6.1.1.c and the "Containment AirLocks" SR 4.6.1.3.a willbe revised to delete the "41 psig" specification of P,. (P, willbe specified in TS 6.8.4.k, "Containment Leakage Rate Testing Program.")
The "Containment Vessel Structural Integrity" SR 4.6.1.6.1-will be revised to stipulate that "Additional inspections shall be conducted during two other refueling outages before the next Type A test ifthe interval for the Type A test has been extended to 10 years." The Basis for TS 3/4.6.1.6 willbe revised to indicate that a visual inspection in conjunction with the Containment Leakage Rate Testing Program is sufficient to demonstrate the containment structural integrity.
Basis The change meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the followingreasons:
1.
As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.
The proposed amendment does not result in a significant change in the types or significant increase in the amounts of any effluents that may be released offsite. The proposed changes do not involve any new equipment or require existing systems to perform a different type of function than they are currently designed to perform. The changes do not introduce any new effluents or increase the quantities of existing effluents.
As such, the changes cannot affect the types or amounts of any effluents that may be released offsite.
The proposed amendment does not result in an increase in individual or cumulative occupational radiation exposure.
Implementation of a performance-based containment leakage rate testing approach willallow test intervals to be based on system and component performance.
Therefore, the increased test intervals that are permitted under a performance-based leakage testing program are actually expected to decrease cumulative occupational exposure.
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SHEARON HARRIS NUCLEARPOWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CONTAINMENTINTEGRATEDLEAKAGERATE TESTING PAGE CHANGE INSTRUCTIONS Removed Pa e
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