ML20096G852

Proposed Tech Specs Changes Providing Limiting Condition for Operation on Containment Structural Integrity & Requiring Retesting of One Tendon from Each Group at Each Physical Insp to Develop Test History & Correlate Test Data

ML20096G852
Person / Time
Site:	Point Beach
Issue date:	09/05/1984
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20096G844	List: ML20096G841 ML20096G852
References
TAC-54989, TAC-54990, NUDOCS 8409110180
Download: ML20096G852 (8)

Text

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Containment Purge Supply and Exhaust Valves h contalment? purge supply and exhaust valves shall be locked closed

- and may not_be opened unless the -reactor is in the cold shutdown or re-fueling shutdown condition.

,1 D.

Containment Structural Integrity

. The structural integrity of the reactor con 6h=nt shall be maintained in accordance with the surveillance criteria specified in 15.4.4.V and i

i 15.4.4.VII.

. 1.

If more than one tendon is observed with a prestressing force between the predicted loer limit (PLL) and 90% of the PLL or if one tendon is observed with prestressing force less than 90% of the PLL, the terx3on(s) shall be restored to the required level of integrity with-in 15 days or the reactor shall be in hot standby within the next six hours 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 />. An engineering evaluation of the situation shall be conducted and a special report subnitted in accordance with specification 15.4.4.VII.D within 30 days.

-2.

With an abnormal degradation of the contaiment structural integrity in excess of that specified in 15.3.6.D.1, and at a level below the acceptance criteria of specification 15.4.4.VII, restore the con-

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taiment structural integrity to the required level within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or j

i be in hot shutdown within the next six hours and in cold shutdown l

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within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Perform an engineering evaluation of the containment structural integrity and provide a special report in j

accordance with specification 15.4.4.VII.D within 30 days.

Basis I

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The Reactor Coolant System conditions of cold shutdown assure that no

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steam will be formed and hence there would be no pressure buildup in i

the contaiment if the Reactor Coolant System ruptures.

B409110180 840905 PDR ADOCM 05000266 P

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15.3.6-2 l

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'1he shutdown conditions of the reactor are selected based on the type of activities that are being carried out. M en the reactor head is not to be removed, the specified cold shutdown margin of 1% AK/K pre-cludes criticality under any occurrence. During refueling the reactor is suberitical by 10% AK/K. '1his precludes criticality under any ciremstarces even though fuel is being moved or control rods with-drawn. Positive reactivity addition by rod motion fr m an initial 10%

oK/K subcritical reactor condition precludes criticality because the reactor would be substantially subcritical even if all control rods were ccupletely withdrawn. Positive reactivity changes by boron

~ dilution may be required or small fluctuations may occur during pre-paration for, recovery frm, or during refueling but mintaining the boron concentration greater than 1800 ppn precludes criticality under f

any circumstances. Should continuous dilution occur, the time inter-vals for this incident are discussed in Section 14.1.5 of the FSAR.

Regarding internal pressure limitations, the contaiment design pres-sure of 60 psig would not be exW if.the internal pressure before a major loss-of-coolant accident were as mch as 6 psig. III

'1he contaiment is designed to withstand an internal vacum of 2.0 psig. (2)

'1he contaiment purge supply and exhaust valves are required to be locked closed during plant operations since these valves have not been denonstrated capable of closing frm the full open position during a design basis loss-of-coolant accident. Maintaining these valves locked closed during plant operation ensures that excessive quanti-ties of radioactive materials will not be released via the contain-

- ment purge syst s in the event of a design basis loss-of-caolant accident. '1he contaiment purge supply and exhause valves will be locked closed by providing locking devices on the control board oper-ators for these valves.

References (1) FSAR - Section 14.3.4 (2) FSAR - Section 5.5.2 -

Unit 1 Amendment 64 Unit 2 Amendment 69 15.3.6-3 October 24, 1982 r..

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VI. CCNIADGENT MCDIFICATICES Any major modification or replacement of ccmponents of the contalment performed after the initial preoperational leakage rate test shall be followed by either an integrated leakage rate test, or a local leak detection test and shall meet the acceptance criteria of I.B and II.B, respectively.

Modifications or replacements performed directly prior to the conduct of an integrated leakage rate test shall not require a separate test.

VII. TENDCN SURVRTT.TANCE A..

Cbject In order to insure containment structural integrity, selected tendons shall be periodically inspected for synpu-s of material deterioration or lift-off force reduction. The tendons for inspection shall be ran-dcely but representatively selected frm each group for each inspection; however, to develop a history and to correlate the observed data, one tendon from each group shall be kept unchanged after initial selection.

Tendons selected for inspection will consist of five hoop tendons, three vertical tendcms located approximately 120' apart, and three dome tendons, one frm each of the three dome tendon groups.

B.

Frequency Tendon surveillance shall be conducted at five-year intervals in accordance with the following schedule:*

Surveillance Unit Year

_ Required 1

1984 Pb/sical 2

1984 Visual 1

1989 Visual 2

1989 Physical

• Subsequent five-year interval inspections repeat this pattern.

15.4.4-8

h C.

Inspections Tendon surveillance in accordance with 15.4.4.VII.B shall consist of either a visual or physical inspection.

(1). Visual Inspection Tendon anchorage assembly hardware of the randomly a.

selected tendons shall be visually examined to the

- extent practicable without dismantling load bearing wwents of the anchorage. 'Ihe imediate concrete area shall be checked visually for indications of

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abnormal material behavior.

(2) Physical Ir g etion Tendons which are physically inspected shall first be a.-

visually inspected in accordance with C. (1).

b.

All tendons which are physically inspected shall be f

subjected to a liftoff test to nonitor their i

prestressing force.

(i)

If th prestressing force of a selected tendon in a group lies above the predicted lower limit, the tendon is considered to be acceptable.

(ii) If the prestressing force of a selected tendon lies between the predicted lower limit and 90%

of the predicted lower limit, two tendons, one on each side of the test tendon, shall be

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checked for their prestressing forces. If the prestressing forces for these tendons are above the predicted lower limit for the tendons, all three tendons shall be restored to the required level of integrity. A single deficiency shall be considered unique and acceptable. If the prestressing force of either of the adjacent te:vions falla below the predicted lower limit of the tendon, additional lift-off testing should be done if necessary, so that the cause and ex-tent of such occurrence can be deterndned and the condition shall be considered an abnormal degradation of the contaiment structure and the provisions of specification 15.3.6.D are applicable.

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(iii)If the prestressing force of the selected test tendon falls below 90% of the predicted lower limit, the tendon shall be ocmpletely detensioned and a determination shall be made as to the cause of the conditica. Such a condition shall be considered an abnormal degradation of the containmant structure and the provisions of specification 15.3.6.D are applicable.

(iv) If the average of all measured tendon forces for

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each group (wrrected for average condition) is found to be less than the minimun required pre-stress level at Anchorage location for that group, l-the condition should be considered as abnormal de-l gradation of the contairrnent structure and the j

provisions of 15.3.6.D are applicable. The average j

mininun design values adjusted for elastic losses l

i are as follows:)

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Hoop 134.5 ksi Vertical 140.6 ksi l

Dczne 137.4 ksi a

One randcznly selected tendon frm each group of c.

tendons shall be subjected to ccmplete detensioning in order to identify broken or damaged wires. During the retensioning of the detensioned tendon, sinultaneous measurements of elongation and jacking force shall be l

made at a mininun of two levels of force between the required seating force and zero. During the detensioning and retensioning of the tendons tested, if the elongation corresponding to a specific load differs by more than 5%

frm that recorded during installation of the tendons, an investigation shall be made to ensure that such discrepancies are not rclated to wire failures or slippage of wires in anchorages.

d.

A tendon wire shall be removed frm the one tendon frm each group which has been ocznpletely detensioned.

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The wire shall be inspected over its entire length to determine if evidence of corrosion or other deleterious effects are present. Tensile tests shall be made on three sanples cut from each reoved wire.

The saples will be cut fran the midsection and each end of the removed wire. Failure of the material to demon-strate the mininun required tensile strength of 240,000 psi shall be considered an abnormal condition of the containment structure and the engineering evaluation provisions of specification 15.3.6.D.1 are applicable.

If an acceptable justification for continued operation cannot be concluded from this evaluation, then the shut-down requirements of specification 15.3.6.D.1 are appli--

cable.

'ihe sheathing filler grease, will be sanpled and inspected e.

on each physically inspected tendon. The operability of u

the sheathing filler grease shall be verified by assuring:

1)

There are no voids in the filler material in excess of 5% of net duct volume.

2)

Complete u se coverage exists for the different m

parts of the Anchorage system, and 3)

The cWim1 properties of the filler material are within the tolerance limits specified by the manu-facturer.

D.

Reports

-A final report documenting the results of each tendon surveillance will be prepared and maintained as a pamanant plant record.

Abnormal conditions observed during tecting will be evaluated to determine the effect of such conditions on contalment struc-tural integrity. This evaluation should be empleted within 30 days of the identification of the condition. Any conditicn which is de-termined in this evaluation to have a significant adverm effect cn con 64r=nt structural integrity will be considered an abnormal de-gradation of the containment structure.

15.4.4-10a l

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Any abnormal degradation of the contaiment structure identified during the engineering evaluation of abnormal conditions shall be re-

~ ported to the U. S. Nuclear Regulatory Ca mission, Office of Inspec-tion and Enforcement, Region III within thirty days of that determina-tion. Other conditions that indicate possible effects on the integ-rity of two or more tendons shall be reportable in the same manner.

Such reports shall include a description'of the tendon condition, the condition of the concrete (ewially at tendon anchorages), the in-spection procedure and the corrective action taken.

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15.4.4-10b

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'Ihe purpose of the leakage tests of the isolation valves in the conMmmt purge supply and exhaust lines is to identify excessive degradation of the resilient seals for these valves. With the excep-

' tion of the test frequency and acceptance criteria, leakage tests of the containment purge sapply and exhaust valves shall be conducted.

in accordance with 15.4.4.III.

4 References (1) FSAR Section 5.1.2.3 l(2) FSAR Section 5.1.2 (3) FSAR Section 14.3.5 (4) FSAR Section 14.3.4 (5) FSAR Section 6.2.3 (6) FSAR pages 5.1-86 & 87 l

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15.4.4 -16

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