ML20247L624

Amend 46 to License NPF-30,revising Tech Specs Section 3/4.6.1.6, Containment Vessel Structural Integrity, to Provide Both Clarification & Relaxation of Some Existing Surveillance Requirements

ML20247L624
Person / Time
Site:	Callaway
Issue date:	05/24/1989
From:	Hannon J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20247L629	List: ML20247L624 ML20247L631
References
NUDOCS 8906020223
Download: ML20247L624 (8)

Text

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' UNITED STATES g,

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NUCLEAR REGULATORY COMMISSION D.

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- WASHINGTON, D. C. 20555

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UNION ELECTRIC. COMPANY T

CALLAWAY PLANT, UNIT 1 DOCKET NO. STN 50-483

-AMENDMENT TO FACILITY OPERATING LICENSE

.Amenon.ent No. 46 License No. NPF-30 o

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1.

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

A.

.The application for amendment filed by Union Electric Company

(UE, the licensee) dated September 18, 1985, as supplemented

'by letters' dated March 23 and May 9, 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, the provisions of the Act, and the rules and regulations of' the Comission; C.

Thereisreasonableassurance(1)'thattheactivitiesauthorized 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 Comission's regulations; D.

The issuance of this amendrent 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 been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

NPF-30 is hereby amended to read as follows:

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t.. (2)-TechnicalSpecifications.andEnvironmentalProtection. Plan The Technical Specifications contained in Appendix A, as revised '

through Amendment No. 46, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license. UE shall operate the facility l-

.in:accordance with the Technical Specifications and the Environmental Protection Plan.

3. -This license amendment is effective upon issuance and shall be implemented within 30 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

' 4to John N.Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, V and Special Projects Office of-Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

May'24, 1989

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ATTACHMENT T0. LICENSE. AMENDMENT N0. 46 L

OPERATING. LICENSE NO. WPF-30 00CKET NO. 50 483 Revise Appendix A Technical Specifications by removing the pages identified

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below and inserting the enclosed pages. The revised pages are identified by

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the captioned amendment number and contain marginal lines indicating the area of change. Corresponding overleaf pages are provided to maintain document completeness.

REMOVE INSERT 3/4 6-8 3/4 6-8 3/4 6-9 3/4 6-9 3/4 6-10 3/4 6-10 3/4 6-10a

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l CONTAINMENT SYSTEMS AIR TEMPERATURE LIMITING CONDITION FOR OPERATION 3.6.1.5 Primary containment average air temperature shall not exceed 120*F.

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

ACTION:

With the containment average air temperature greater than 120'F, reduce the average air temperature to within the limit within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 />.

SURVEILLANCE REQUIREMENTS

4. 6.1. 5 The primary containment average air temperature shall be the arithmetical average of the temperatures at the following locations and shall be determined at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:

Location a.

Containment Cooler Inlet located near NNE wall (El 2068'-8");

b.

Containment Cooler Inlet located near West wall (El 2068'-8");

c.

Containment Cooler Inlet located near NNW wall (El 2068'-8"); and d.

Containment Cooler Inlet located near East wall (El 2068'-8").

CALLAWAY - UNIT 1 3/4 6-7

CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.6 The structural integrity of the containment vessel shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.1.6.

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

ACTION:

a.

With the abnormal degradation indicated by the conditions in Specification 4.6.1.6.la.4, restore the tendons 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 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 vessel to the required level of integrity or verify that containment integrity is maintained within 15 days and perform an engineering evaluation of the containment 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 4.6.1.6.1 Containment Vessel Tendons. The structural integrity of the pre-stressing tendons of the containment vessel shall be demonstrated at the end of 1.5, 3.5 and 5.5 years following the initial containment vessel structural integrity test and at 5-year intervals thereafter. The structural integrity of the tendons shall be demonstrated by:

a.

Determining that a random but representative sample of at least 11 l

tendons (4 inverted V and 7 hoop) each have an observed lift-off force within the predicted limits established for each tendon.

For each subsequent inspection one tendon from each group (1 inverted U and 1 hoop) shall be kept unchanged to develop a history and to correlate the ooserved data.

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

CALLAWAY - UNIT 1 3/4 6-8 Amendment No. E, 46

j CONTAINMENT SYSTEMS i

CONTAINMENT VESSEL STRUCTURAL INTEGRITY SURVEILLANCE REQUI.,EMENTS (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 adjacent (accessible) tendons, one on each side of this tendon shall be checked for their pre-l stressing 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 of such occurrence. The condition shall be considered as an indication of abnormal degradation of the containment structure, 3.

If the measured prestressing force of any tendon lies below 90% of the prescribed lower limit, the defective tendon shall be completely detensioned and additional lift-off testing i

shall be done so as to determine the cause and extent of such occurrence. The condition shall be considered as an indica-tion of abnormal degradation of the containment structure, i

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 locations for that group, the condition shall be considered as abnonnal degradation of the containment structure, 5.

If from consecutive surveillance 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 done 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, and 6.

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

CALLAWAY - UNIT 1 3/4 6-9 Amendment No. 46

CONTAINMENT SYSTEMS i

CONTAINMENT VESSEL STRUCTURAL INTEGRITY l

SURVEILLANCE REQUIREMENTS (Continued) b.

Performing tendon detensioning, inspections, and material tests on

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a previously stressed tendon from each group. A randomly selected

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tendon from each group shall be completely detensioned in order to identify broken or damaged wires and determine that over the entire 1ength of the removed wire sample (which shall include the broken wire if so identified) that:

1.

The tendon wires are free of corrosion, cracks, and can. ge, and 2.

A minimum tensile strength of 240 ksi (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 considered as an indication of abnormal degradation of the containment structure.

c.

Performing tendon retensioning of those tendons detensioned for I

inspection to at least the force level recorded prior to deten-I sioning or the predicted value, whichever is greater, with the tolerance within minus zero to pias 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 shall be measured simultaneously at a minimum of three approximately equally spaced levels of force between zero and the seating force.

If the elongation corresponding to a specific load differs by more than 10% from that recorded during the installation, an investigation shall be made to ensure that the difference is not related to wire failures or slip of wires in anchorages. This condition shall be considered as an indication of abnormal degradation of the contain-ment 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 does not exceed 5% of the net duct volume, when injected at + 10% of the specified installation j

pressure, CALLAWAY - UNIT 1 3/4 6-10 Amendment No. 46

l CONTAINMENT SYSTEMS CONTAINMENT VESSEL STRUCTURAL INTEGRITY SURVEILLANCE REQUIREMENTS (Continued) 3.

Minimum grease coverage exists for the different parts of the anchorage system, 4.

During general visual examination of the containment exterior surface, that grease leakage that could affect containment

-integrity is not present, and 5.

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

Wa'ter Content 0-10% by dry weight Chlorides 0-10 ppm i

Nitrates 0-10 ppm Sulfides 0-10 ppm Reserved Alkalinity

>0 Failure to meet the requirements of 4.6.1.6.1.d shall be considered as an indication of abnormal degradation of the containment structure.

I 4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces. As an assurance of the structural integrity of the containment vessel, tendon anchorage assembly hardware (such as bearing plates, stressing washers, wedges, and buttonheads) of all tendons selected for inspection shall be visually examined. Tendon anchorages selected for inspection shall be visually examined to the ex+ent practical without dismantling the load bearing components of the anchorages.

Bottom grease caps of all vertical tendons shall be visDally inspected to detect gresse leakage or grease cap deformations.

The surrounding concrete shall also be checked visually for indicatien of any abnormal condition. The frequency of this surveillance shall be in accordance with 4.6.1.6.1.

Signif-l icant grease leakage, grease cap defo m tion or abnormal concrete condition shall be considered as an indication cf abnormal degradation of the containment structure.

4.6.1.6.3 Containment vessel Surfaces. The exterior surface of the contain-ment shall be visually examined to detect art.as of large spall, severe scaling, D-cracking in an area of 25 sq. ft. or more, other surface deterioration or disintegration, or grease leakage, each of which shall be considered as evidence of abnormal degradation of structural integrity of the containment.

This inspection shall be performed piior to the Type A containment leakage rate test.

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l CALLAWAY - UNIT 1 3/4 6-10a Amendment No. 46 E__