ML20055H150

Amends 18 & 8 to Licenses NPF-76 & NPF-80,respectively, Changing Tech Specs Re Reactor Containment Bldg

ML20055H150
Person / Time
Site:	South Texas
Issue date:	07/19/1990
From:	Charemagne Grimes Office of Nuclear Reactor Regulation
To:
Shared Package
ML20055H151	List: ML20055H150 ML20055H153
References
NUDOCS 9007250251
Download: ML20055H150 (11)

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UNITED STATES I

NUCLEAR REGULATORY COMMISSION '

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WASHINGTON, D. C. 20666 S....

HOUSTON LIGHTING & POWER COMPANY q

CITYPUBLICSERVICEBOARDOFS'AN,JNTOMIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50 498 SOUTH TEXAS PROJECT. UNIT'1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 18 License No. NPF 1.

The Nuclear Regulatory Commission (the Comission). has found that:

A.

The a plication for amendment by Houston Lighting & Power Company *

(HL&P acting on behalf of itself and for the City Public Service BoardofSanAntonio(CPS),CentralPower'andLightCompany(CPL),

andCityofAustin, Texas (COA)(thelicensees)datedJune 28, 1989, as supplemented on November 29, 1089, complies with the standards and requirements of the Atomic Energy Act of 1954 as amended (th.

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Act), and the Comission's rules and regulations s,et forth in 10 CFR Chapter I-i B.

The facility will operate in conformity with the application, as-amended, the provisions of the Act, and the rules and regulations of the Comission; j

C.

There is reasonable assurance:

(i)thatthe.activitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the-public; and E.

The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Comission's regulations and. all applicable-requirements have l

been satisfied.

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• Houston Lighting & Power Company is authorized to act for the City Public.

Service Board of San Antonio, Central Power and Light Company and City 'of-Austin, Texas.and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

9007250251 900719

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Accordingly, the license is aranded by changes to the. Technical.Specifi-cations-as indicated in the attachnent to this license amendrent and 1

Paragraph 2.C.(2) of facility Operating License.No..NPF-76 is hereby l

amended to read as follows:

2.

Technical.Spetifications The The G esi specifications contained in Appendix A, as revised-through Amendt.cnt.No.18, and the Environmental Protection Plan '

f contaii,d in.\\prendix B, are hereby incorporated in the license.

The lic.nsee saall operate the facility in accordance with the Technic 61 Specifications and the-Environmental Protection Plan.

3.-

The license anendment is-effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY.COMMISS10t'

' rI.GrimeM,4 Christo Director Project Directorate IV-2 Division of Reactor Projects - III, IV,-V and Special. Projects l

Office of Nuclear Reactor Regulation At.tachn.ent:

l Chences to the Technical

. Specifications Date of Issuance:

July.19, 1990 I

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UNITED STATES 4

NUCLEAR REGULATORY COMMISSION g

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WASHINGTON D. C. 20865 HOUSTON LIGHTIHC & PulER COMPANY CITY PUBLIC SERVICE BOARD 0F SAN ANTONIO CENTRAL POWER AND LIGH"' COMPANY CITY OF AUSTIN. TIXAS DOCrrT NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 i

AMENDMENT TO FACILITY OPERATING ~ LICENSE I

1 I

Amendment No. 8 License No. NPF-80 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Houston Lighting & Power Company *

(HL&P) acting on behalf of itself and for the Citv ruolic Service Board of San Antonio (CPS)(, Central Power and '.ight Company (CPL),

and City of Austin, Texas C0A)(thelicensees)datedJune 28, 1989, 4

as supplemented on November 29,-1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the.

Act), and-the Comission's rules and regulations set forth in 10:CFR Chapter-I; B.

The facility will operate in conformity with the application, as

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j amended.- the provisions of the Act, and the rules and regulations-of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendn.ent can be conducted without endangering the' health.

and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; y

D' The issuance of this license amendment will not be inimical to thel comon defense and security or to the-health and: safety of the public;

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E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and.all applicable requirements have been satisfied.

• Houston Lighting & Power ~ Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility -and control over the physical construction,Eoperation and maintenance of the facility.

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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and-Paragraph 2.C.(2) of Facility Operating License No. NPF-80 is hereby amended to read as follows:-

2.

Technical Specifications ~

The Technical Specifications contained in Appendix A,.as revised through Amendment No. 8,-and the Environmental Protection Plan i

contained in Appendix B, are hereby incorporated in the license.

The licensee shall_ operate the facility in accordance with the

-u Technical Specifications and the Environmental' Protection Plan.

3.

The license-amendment is' effective as of.its-date of issuance.

- FOR THE NUCLEAR REGULATORY CCfTISSION hr.ist her I. Gri Director l

- Pro.iect Directorate IV-2 Di.. lon of Reactor Projects - III, IV, V'and'Special Projects Office of Nuclear Reactor Regulation

Attachment:

charges to the Technical Specifications Date of-Issuance:

July 19, 1990 4

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ATTACHMENT TO LICENSE AMENDMENT NOS.18 AND 8 -

FACILJTYOPERATINGLICENSENOS.NPF-76'ANDNPF-80 D0CKET-NOS.-50-498 AND 50-4_99 Replace-the following pages of the Appendix A Technical Specifications with the attached pages. Tae revised pages are identified b contain vertical lines indicating the areas of. change. y Amendment number and The corresponding overicaf.pages are also provided to a.aintain document completeness.

Remove-Insert-s 3/4 6-9 3/4 6-9 3/4 6-10 3/4'6-10 3/4 6-11 3/4 6-11 3/4 6-11a 3/4 6-11b 1

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-CONTAINMENT SYSTEMS-CONTAINMENT-STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION

3. 6.1. 6 The structural integrity of the containment (s).shall-be maintained at

-l-a level consistent with the acceptance criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTICN:

a.

With the abnormal degradation indicated by the conditions in Specification 4.6.3.6.la.'4, restore the containment (s) to the-

-required level of integrity or verify that containment. integrity is-maintained within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and perform an engineering evaluation of-the containment (s) and provide a Special Report to the Commission within 15 days in accordance with Specification:6.9.2 or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN-within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.

With the indicated abnormal degradation of' the structural integrity other than ACTION a. at a level below the acceptance criteria of-Specification 4.6.1.6, restore the containment (s) to the' required level of integrity or verify. that containment integrity is maintained within 15 days,-perform an engineering evaluation of;the contain-ment (s) and provide a-Special-Report to the Commission within 30 days in accordance with Specification 6.9.2 or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

The provisions of Specification 3.0.4 are not applicable, SURVEILLANCE REQUIREMENTS

4. 6.1. 6 CONTAINMENT PRESTRESSING SYSTEM The structural integrity of the prestressing tendons of the containment shall be demonstrated at the end of 1, 3, and 5 years following_the-initial containment structural-integrity test and at.5 year intervals thereafter..The inspection schedule for lift-off testing-shall' be as-shownLin Figure 4.6-1.

4.6.1.6.1 The adequacy of prestressing forces in tendons shall be=

demonstrated by:

a.

Determining that a random but representative sample of at least 10-tendons (6 hoop, 4 interverted U) each have an observed lift-off force within predicted limits established for each tendon.

For each subsequent inspection, one tendon from each group shall be kept unchanged to develop a history and to correlate the observed data.

The procedure of inspection and the tendon acceptance criteria shall be as follows:

SOUTH TEXAS - UNITS 1 & 2 3/4 6-9 Unit 1 - Amendment No.18 Unit 2 - Amendment No. 8

CONTAINMENT SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) 1)

If the measured prestressing force of the selected tendon in a group lies.above the prescribed lower limit, the lift-off test is considered to be a positive indication of the sample tendon's acceptability.

2)

If the measured prestressing force of the selected tendon in a group lies between the prescribed lower limit and 90% of the prescribed lower limit, two tendons :one on each side of this-tendon shall be checked for their prestressing forces.

If the prestressing forces of these two tendons are above 95% of the prescribed lower limits for the tendons, all three-tendons shall be restored to the required level of integrity, and the tendon group shall be considered as acceptable.

If the.

measured prestressing force of any two tendons falls below 95%

of the prescribed lower limits of the tendons, additional lift-off testing shall be done to detect the cause and extent I

of such-occurrence. The conditions;shall be considered as an indication of abnormal degradation of the containment structures.

3)

If the measured prestressing force of any tendon lies below 90%

of the prescribed lower limit, an engineering investigation will be performed to determine the cause and extent of the occurrence.. The condition shall be considered as an indication of abnormal degradation of the containment stra cure.

4)

If the average.of all measured prestressing forces for each group (corrected for average condition) is-found to be less, than the minimum required prestress level at the anchorage location for that group, the condition sh-" be ec...idered as abnormal degradation of the containmeni, strsdure.

5)

If from consecutive surveillances, the measured prestressing forces for the same tendon or tendons in a group indicate a-trend of prestress loss larger than expected and the resulting prestressing-forces;will-be less than the minimum required for the group before the next scheduled surveillance, additional-lift-off testing shall be tone so as to determine the cause and extent of such occurrence.

The condition shall be considered as an indication of abnormal degradation of the containment structure.

6)

Unless there is abnormal degradation of the containment during the first three inspections, the sample population for subsequent inspections shall include at least 6 tendons (3 hoop 3 inverted U).

I SOUTH TEXAS - UNITS 1 & 2 3/4 6-10 Unit 1 - Amendment No.18 Unit 2 - Amendment No. 8 1

CONTAINMENT SYSTEMS-SURVEILLANCE REQUIREMENTS (Continued) b.

Performing tendon detensioning, inspections, and material tests 9n a previously. stressed tendon.

Two tendons, one from each group shall be.detensioned each time lift-offs are performed per Figure 4.6-1.

A randomly selected tendon shall be completely detensioned in order to identify broken or damaged wires and determining that over the entire length of the removed wire sample (which should include the broken wire if so identified) that:

1)

The tendon wires are free of corrosion, cracks, and damage, and 2)

A minimum tensile strength of 240,000 psi (guaranteed ultimate strength of the tendon material) exists for at least three wire -

samples (one from each end and one at mid-length) cut from each removed wire.

Failure to meet the requirements of 4.6.1.6.1.b shall be l

considered as an indication of abnormal degradation of the containment structure, c.

Performing tendon retensioning of those tendons detensioned for inspection to at least the force level recorded prior to detensioning or.the predicted value, whichever is greater, with the tolerance within minus zero to plus six percent (6%), but not to exceed 70% of the guaranteed ultimate tensile strength of the tendons.

During retensioning of these tendons, the changes in load and elongation should be measured simultaneously at a minimum of three approximately equally spaced levels of force.

If the elongation corresponding to a specific load differs by more than 10%

from that recorded during the installation, an investigation should be made to ensure that the difference is not related to wire failures.

This condition shall be considered as an indication of abnormal' degradation of the containment structure, d.

Verifying the OPERABILITY of the sheathing filler grease by assuring:

1)

There are no changes in the presence or physical appearance of the sheathing filler grease including the presence of free water.

2)

Amount of grease replaced in excess of the grease removed does not exceed 5% of the net duct-volume, when injected at a pressure not to exceed the designer's specifications.

3)

Minimum grease coverage exists for the different parts of the anchorage system.

4)

General visual examination of the containment exterior surface does not exhibit the grease leakage that could affect containment integrity, and

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SOUTH TEXAS - UNITS 1 & 2 3/4 6-11 Unit 1 - Amendment No. 18 Unit 2 - Amendment No. 8 U

1 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 5)

The chemical properties of the filler material are within the tolerance limits specified as follows:

l Water Content 0 - 10% (by. dry wt.)

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-Chlorides 0 - 10 ppm Nitrates 0 - 10 ppm Sulfides 0 - 10 ppa Reserved Alkalinity 50% of the installed value; (Base Number) 0 (for older grease)

Failure to meet requirement of 4.6.1.6.1.d shall be considered as an indication of abnormal degradation of the containment structure.

4.6.1.6.2 End Anchorages and Ad.iacent Concrete Surfaces.

As an assurance of the structuTal integrity of the containment (s), tendon anchorage assembly hardware (such as bearing plates, stressing washers, wedges, and buttonheads) of all tendons selected for inspection shall be visually examined.

During combined inspection (See Figure 4.6-1), for the containment not having full inspection, only visual inspection need to be performed.

The' sample size for visual only inspection is-the same as for full inspection (see 4.6.1.6.1.a).

Tendon anchorages selected for inspection shall be visually-examined to the extent practical without dismantling the load bearing components of the anchorages.. Bottom grease-caps of all vertical tendons shal1~be visually inspected to detect grease leakage or grease cap deformations.

The surrounding concrete should also be checked visually for indication of any-abnormal condition.

Significant grease leakage, grease cap deformation or abnormal concrete condition shall be considered as an indication of abnormal degradation.of containment structure.

4 4.6.1.6.3 Containment Surfaces.

The exterior surface of the containment (s).

should be visually examined to detect areas of large spall, severe-scaling, 0 cracking in an area of 25 sq. ft. or more, other surface deterioration or l

disintegration, or significant grease leakage, each.of which can be considered as evidence of abnormal degradation of structural integrity of the containment (s).

SOUTH TEXAS - UNITS 1 & 2 3/4 6-11a Unit 1 - Amendment No.18 Unit 2 - Amendment No. 8 2

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i TINE AFTER INITIAL STRUCTURAL INTEGRITY TESTING 'OF CONTAINNEirT, YEARS (Liftoff Testinn. schedule, Containment No.'2).

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PP Figure 4.F.i m-Schedule for. Lift-offLTesting.

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CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valve shall be

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OPERABLE and:

i Each 48-inch containment shutdown purge supply and exhaust isola-a.

tion ' salve shall be closed and sealed closed, and l

b.-

The 18-inch supplementary containment purge supply and exhaust jolation valves shall be closed to the maximum extent practicable but may be.open for supplementary purge system operation for presa sure control, for ALARA and respirable air quality considerations for personnel entry and for surveillance tests that require the-l valves to be open.

APPLICABILITY:

MODES 1, 2, 3, and 4.

l ACTION:

With a 48-inch containment purge supply and/or exhaust. isolation a.

valve open or not-sealed closed, close and/or seal close that valve or isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise be in at-least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.-

With~ the 18-inch supplementary containment purge supply and/or exhaust isolation valve (s) open for reasons other than given in Specification 3.6.1.7.b. above, close the open 18-inch valvo(s) or isolate the penetration (s) within-4 hours, otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOWN within the i

following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, With a containment purge-supply and/or exhaust. isolation valve (s) c.

having a measured leakage rate in excess of the-limits of Specifi-cations 4.6.L 7.2 and/or 4.6.1.7.3, restore the inoperable valve (s) to OPERABLE status or isolate the penetrations so that-the measured leakage rate does not exceed the limits of Specifications 4.6.1.7.2 and/or 4.6.1.7.3 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOWN within-the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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SOUTH TEXAS - UNITS 1 & 2 3/4 6-12

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