ML20116F093

Proposed Tech Specs Re Elimination of Corrosion Testing Requirement for SG Tube Sleeving

ML20116F093
Person / Time
Site:	Byron, Braidwood
Issue date:	08/02/1996
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20116F081	List: ML20116F079 ML20116F093
References
NUDOCS 9608060236
Download: ML20116F093 (9)

Text

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I ATTACHMENT B s

MARKED UP PAGES FOR PROPOSED CHANGES TO FACILITY OPERATING LICENSES NPF-37, NPF-66, NPF-72, AND NPF-77 l

BYRON STATION UNIT 1 LICENSE BRAIDWOOD STATION UNIT 1 LICENSE REVISED PAGE:

REVISED PAGE:

NPF-37 page 5 NPF-72 page 3a BYRON STATION UNIT 2 LICENSE BRAIDWOOD STATION UNIT 2 LICENSE REVISED PAGE:

REVISED PAGE:

hPF-66 page 2a NPF-77 page 3a l

4 knba bybwd stmgenslascorrfdoc 5 9600060236 960802 PDR ADOCK 05000454 P

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. NPF-37 (Continued) l (15) Use.of advisors who were licensed only at the RO l

level will be evaluated on a case-by-case basis.

Advisors shall be trained on plant procedures, technical specifications and plant systems, and l

shall ne examined on these topics at a level sufficient to assure familiarity with the plant.

For each shift, the remainder of the shift crew shall be trained as to the role of the advisors.

These advisors shall be retained until the experience levels identified in the first sentence above have been achieved.

The NRC shall be notified at least 30 days prior to the date that the licensee proposes' to release'the advisors from further service.

(1 Steam Generator Sleeving Corrosion Testing The icensee shall conduct addition corrosion testin to establish the design e for the laser l

welded s ed tubes in the pr ence of a crevice.

The corrosichstesting shall emonstrate the corrosion resista ce for e laser welded joints l

in tubes that boun h material parameters in the steam generators.

e orrosion testing results shall be reviewe nd acc 'ted by the Nuclear Regulatory Co ssion prior the Beginning-of-Cycle 9.

I conformance with t requirements of the plan echnical Specifications r tube struc al integrity is not confirme,

he tubes con Ining the sleeves in question shall oved from service.

D.

The facility requires exemptions from certain requirements of Appendices A, E and J to 10 CFR Part i

50.

These include (a) an exemption from the requirements of Paragraph III.D.2 (b) (ii) of Appendix J, the testing of containment air locks at times when containment integrity is not required (Section 6.2.6 of the SER), (b) an exemption from GDC-2 of Appendix A, the requirement that structures, systems pnd components important to safety be designed to withstand the effects of natural phenomena such as earthquakes (Section 3.10 of SSER #5), (c) an exemption from GDC-13 and GDC-17 of Appendix A, the requirement that instrumentation be provided to monitor variables and systems over their anticipated ranges, and the requirement that provisions be included to minimize the probability of losing electric power (Section 9.5.4.1 of SSER #5), (d) an exemption from GDC-19 of Appendix A, the requirement that the control room have adequate radiation protection to permit access and occupancy under accident conditions (Section 6.5.1 of SSER #6),

and (e) an exemption from the requirement of Section IV.F of Appendix E that a full participation emergency i

planning exercise be conducted within one year before issuance of the first operating license for full power and prior to operation above 5% of rated power (Section t

. Amendment 83 ks/nla/ byron / amend /7

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(5?ssSteam Generator Sleeving Corrosion Testing The nsee shall conduct additional corrosion t g

to estab sh_the design ~ life for the laser w I

l sleeved tubes the presence of a crev' The i

corrosion testing 11 demonstrat

. e corrosion l

resistance for the la wel oints in tubes that I

l bound the material para in the steam generators.

The corrosion test' results 11 be reviewed and accepted by t uclear Regulator ommission prior to the Begi

' g-of-Cycle 8.

If conform e with the re

' ements of the plant Technical Speci ations for u e structural integrity is not confirmed, t tubes containing the sleeves in question shall be remov from service.

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Amendment 83 ks/nla/ byron / amend /13

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Steam Generator Sleeving Corrosion Testing The.

nsee shall conduct additional corrosion tes to establis design life for the laser welded eved tubes in the presen f a crevice.

The corros esting shall demonstrate the co lon resistance the laser welded

-joints in. tubes that bo the rial parameters in the steam generators.

The cor testing results shall be reviewed and accepte the Nuc Regulatory Commission prior to the Be Ing-of-Cycle 7.

nformance with the requiremen the plant Technical Speci tions for tube strue integrity is not confirmed, the tub ontaining the sleeves in question shall be removed from servi D.

The facility requires an exemption from the requirements of Appendix J to 10 CFR Part 50, Paragraph III.D.2 (b) (ii), the testing of containment air locks at time when containment integrity is not required (SER Section 6.2. 6).

This exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security.

This exemption is hereby granted.

The special circumstances regarding this exemption are identified in the referenced section of the safety evaluation report.and the supplements thereto. -This exemption is granted pursuant to 10 CFR 50.12.

With this exemption, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

An exemption was previously granted pursuant to 10 CFR 70.24.

The exemption was granted NRC materials license No. SNM-1938, issued October 8, 1985 and relieved the license from the requirement of having a criticality alarm system.

Therefore, the licensee is exempted of having criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

E.

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, as supplemented and amended, and as approved in the SER dated November 1983 and its supplements, subject to the following provisions:

The licensee may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

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k:Watrdwd\\ amends Amendment 75

-3a-Steam Generator Sleeving Corrosion Testing The ensee shall conduct additional corrosion testin establis e design life for the laser welded s d tubes in the presen f a crevic.gx_ The corrosio sting shall l

demonstrate the co sion resistance e laser welded

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joints in tubes that b the ial parameters in the l

steam generators.

The cor

'on testing results shall be l

reviewed and accepted b he Nu ear Regulatory Commission prior to the Be ng-of-Cycle 7.

conformance with the requireme the plant Technical Spec ations for tube l

upt a

integrity is not confirmed, the tu containing i

t sleeves in question shall be removed from serv L

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I k:WatrdwdWmendi12 Amendment 75 l

ATTACHMENT C EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATIONS FOR PROPOSED CHANGES TO FACILITY OPERATING LICENSES NPF-37, NPF-66, NPF-72, AND NPF-77 Commonwealth Edison (Comed) has evaluated this proposed amendment and determined that it involves no significant hazards considerations. According to Title 10 Code of Federal Regulations Section 50 Subsection 92 Paragraph c (10 CFR 50.92 (c)), a proposed amendn'ent to an operating license involves no significant hazards considerations if operation of the facilhy in accordance with the proposed amendment would not:

1.

Involve a significant increase in the probability or consequences of an accident previously evaluated; or 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.

A.

INTRODUCTION Comed proposes to amend the Facility Operating Licenses for Byron Units 1 and 2 and Braidwood Units I and 2. This amendment would remove the license condition to perform additional laboratory corrosion testing to establish the design life for the laser welded sleeved tubes in the presence of a crevice. This license condition was added at the request of the Nuclear Regulatory Commission (NRC) as a condition for Amendments 58 (Byron) and 46 (Braidwood) which approved laser welded sleeving. Comed has taken measures that will allow for the early detection of a sleeve flaw: sleeve joint inservice inspections, the primary-to-secondary leakage limits and the primary-to-secondary leakage monitoring program.

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'NO SIGNIFICANT HAZARDS ANALYSIS t

j 1.

The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

This proposed change only involves deleting laboratory testing requirements designed to demonstrate service life oflaser welded sleeved tubes in the presence of a crevice. Current j

inspection requirements ensure that premature degradation is identified and that tubes containing degraded sleevejoints are plugged. Operational primary-to-secondary leakage limits ensure that i

appropriate action is taken if sleeve degradation results in leakage. These actions will ensure that offsite dose will be maintained within a small percentage of 10 CFR 100 limits. Failure of a sleeve joint is bounded by the Steam Generator Tube Rupture event evaluated in the UFSAR.

Therefore, the laboratory testing to determine service life of sleeved tube joints in the presence of a crevice does not provide any further useful data. The change does not result in the installation j

of any new equipment, and no existing equipment is modified.

Therefore, this proposed change does not involve a significant increase in the probability or

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consequences of an accidem previously evaluated.-

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2.

The proposed change does not create the possibility of a new or different kind of i

. accident from any accident previously evaluated.

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This proposed change only addresses deleting the laboratory testing requirements designed to demonstrate service life of sleeved tubes in the presence of a crevice. Sleeved tubes will continue j

to be inspected and plugged in accordance with existing requirements which are sufficient to j-ensure detection and repair of degraded tubes. Premature degradation of tubes is addressed j

through primary-to-secondary leakage monitoring and leakage limits. No new equipment is being j

installed and no existing equipment is being modified by this proposed change. Also, no new l

system configurations will be introduced as a result of this proposed change. Therefore, no new i

or different failure modes are being introduced by deleting the laboratory testing.

Thus, this proposed change does not create the possibility of a new or different kind of accident i

from any accident previously evaluated.

4 3.

'I he proposed change does not involve a significant reduction in a margin of safety.

This proposed change only involves deleting laboratory testing requirements designed to demonstrate service life of sleeved tubes in the presence of a crevice. Sleeve integrity will be monitored during the operating cycle through the current primary-to-secondary leakage monitoring program. In the event of premature degradation of a sleevejoint that results in tube leakage, plant shutdown will occur as required by Technical Specifications and administrative requirements in accordance with approved plant procedures. Sleeved tubes will be monitored for degradation in accordance with the existing inservice inspection requirements which monitors a k nla bybwd sempermlwecorrf doc.10.

minimum 20% random slceve sample size. Any tubes with defective sleeve joints will be plugged es regtiired by Technical Specifications. Service life of sleeved tubes in the presence of a crevice, as predicted by laboratory testing, does not affect the margin of safety of the plant. Therefore, this proposed change does not involve a significant reduction in a margin of safety.

Based on the above evaluation, Commonwealth Edison has concluded that these changes involve no significant hazards considerations.

k nlu bybwd singens twsconf doc 11 1

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1-ATTACHMENT D-I ENVIRONMENTAL ASSESSMENT FOR PROPOSED CHANGES TO FACILITY OPL ^ ' TING LICENSES NPF-37, NPF-66, NPF-72, AND NPF-77 l

Commonwealth Edison Company (Comed) has evaluated this proposed license amendmunt request against the criteria for identification oflicensing and regulatory actions requiring i

environmental assessment in accordance with Title 10, Code of Federal Regulations, Part 51, l

Section 21 (10 CFR 51.21). Comed has determined that this proposed license amendment request meets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9). This determination is based upon the following-The proposed licensing action involves the issuance of an amendment to a license

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j for a reactor pursuant to 10 CFR 50 which changes a requirement with respect to installation or use of a facility component located within the restricted area, as defmed in 10 CFR 20, or which changes an inspection or a surveillance

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requirement. This proposed license amendment request eliminates the requirement 3

to perform additional laboratory corrosion testing oflaser welded sleeves in the presence of a crevice.

2.

this proposed license amendment request involves no significant hazards I

considerations as~ demonstrated in Attachment C;

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3.

there is no sigmficant change in the types or significant mcrease m the amounts of I

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- any effluent that may be released offsite; and l

4.

there is no significant increase in individual or cumulative occupational radiation l

exposure.

Therefore, pursuant to 10 CFR 51.22(b), neither an environmental impact statement nor an i

environmental assessment is necessary for this proposed license amendment request.

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