ML20217B122

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Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program
ML20217B122
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 10/04/1999
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20217B117 List:
References
RTR-REGGD-01.035 NUDOCS 9910120161
Download: ML20217B122 (10)
v • d • e


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Enclosure 3 -

Vogtle Electric Generating Plant Request to Revise Technical Specifications Prestressed Concrete Containment Tendon Surveillance Program Marked-up TS Pages 1

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9910120161 991004 PDR ADOCK 05000424 P PDR

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TA1;LE OF, CONTENTS LIST OF FIGURES <

2.1.1-1 Re a ctor Co re Safety Limits . ..................... . .......... .. ............... . ............. 2.0-2 3.4.16-1 Reactor Coolant Dose Equivalent 1-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific j Activity > 1 pCi/ gram Dose Equivalent 1-131................................... 3.4.16-4  !

3.7.18-1 Vogtle Unit i Bumup Credit Requirements for All Ce ll S to ra g e . . . . . . . . . . . . . . . . . . . . . .. .. . . . ... . . . .. .. . . . . .. . . . . . . . . .. . . . . . . . . .. .. . . . . . . . . . . . 3.7.18-3 3.7.18-2 Vogtle Unit 2 Bumup Credit Requirements for All Cell S tora g e . .. .. . . . . . ... . .... . .. .. .. .. .. . ... . .. .. .. .. .. . . .. . . .. .. . . . . .. . . . . .. . . .. .. .... .. 3.7.18-4 4.3.1-1 Vogtle Unit 1 Bumup Cre@ Requirements for 3-out-of-4 Sto ra ge ..... .. .. .. . . .. . . . . .... ...... . ... .. .. .. . . .. .. .. . . . . .. .. . . .. .. . . . . . . . . .. . .. . 4.0-6 l 4.3.1-2 Vogtle Unit 2 Bumup Credit Requirements for 3-o ut-of-4 S tora ge . . ... .. .. . ... ... ........ ... . .. . . ... . . . .. .. ..... .. .... .. .. . ...... . .. .. .. .. 4.0-7 j 4.3.1 -3 Vogtle Unit 2 Bumup Credit Requirements for 3x5 l Storage..........................................................................................4.0-8 4.3.1-4 Vogtle Units 1 and 2 Ertpty Cell Checkerboard S tora ge Config urations ....... .... ............ ......... .................................. 4.0-9 4.3.1-5 Vogtle Unit 2 3x3 Checkerboard S;orage Cc nfiguration......................... 4.0-10 4.3.1-6 Vogtle Units 1 and 2 Interface Requiremento (All Cell to Checkerboard Storage).... ... ....................................... 4.0-11 4.3.1-7 Vogtle Units 1 and 2 Interface Requirements l (Checkerboard Storage interface).................................................. 4.0-12 l 4.3.1-8 Vogtle Unit 2 Interface Requirements (3x3 Checkerboard to All Cell Storage)................................ ......... 4.0-13 l 4.3.1-9 Vogtle Unit 2 Interface Requirements i (3x3 to Empty Cell Checkerboard Storage).................................... 4.0-14 l 5.g G l .cwam schedule.o,o of+DR-6f/*

sa sue. 7EsHayEv b - ~- ~ . -- -- 5.5 22 l

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l Vogtle Units 1 and 2 vi Amendment No.107 (Unit 1) l Amendment No. 85 (Unit 2)  !

Programs and Manuals 5.5

., 5.5 Programs and Manuals 5.5.6 Prestressed Concrete Containment Tendon Surveillance Proaram This program provides controls for monitoring any tendon degradation in prestressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structuralintegrity. The prog:am shall include baseline measurements prior to initial operations. hedendom Oc ;;E;r.;; Pi_,, ..., : .;;;:::: '::;_.;c.;~., ...d _;;;; :r.:; ::.:;. .. l . :: L .c.

: ::d . ~ ..... , r~,...~,, ^ _.i '. 00, P.; . ~.. . C.107p The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pump Flywheel Inspection Prooram This program shall provide for the inspection of each reactor coolant pump l flywheel at least once per 10 years by conducting either:

a. An in-place ultrasonic examination over the volume frcm the inner bore of the flywheel to the circle of one-half the outer radius; or
b. A surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the disassembled flywheel.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant Pump Rywheel Inspection Program.

5.5.8 Inservice Testina Prooram  ;

This program provides controls for inservice testing of ASME Code Class 1,2, and 3 components. The program shallinclude the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

(continued)

Vogtle Units 1 and 2 5.9-5 Amendment No.103 (Unit 1)

Amendment No. 81 (Unit 2)

1 i .. 'a INSERT FOR TS 5.5.6 The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Regulatory Guide 1.35, Revision 2,1976, with the following exceptions:

1. Number of Tendons Detensioned - Only one vertical and one horizontal tendon are detensioned on Unit 1 each time lift-offs are performed on Unit 1 per figure 5.5.6-1. Only one vertical or one horizontal tendoa is detensioned on Unit 1 each time lift-offs are performed on Unit 2 per figure 5.5.6-1.
2. Concrete Inspection - The concrete adjacent to the vertical tendons cannot be inspected due to steel plating covering the concrete.

~ 3.' The areas adjacent to the tendons are inspected during the tendon surveillance instead of during the ILRT.

Only the Unit 1 containment is subject to the complete surveillance program. Unit 1 is equipped with selected tendons specifically designed for detensioning. The Unit 2 ,

containment has permanent anchorage assemblies (nondetensionable).

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SAMPLE SIZE CRITERIA 4

4% 2%

01 3 15 25 35 II I I I I TlME AFTER INITIAL STRUCTURAL INTEGRITY TESTING OF CONTAINMENT, YEARS (Lift-off Testing Schedule, Containment No.1) 0 .3 5 15 25 35 I II I I I TIME AFTER INITIAL STRUCTURAL INTEGRITY TESTING OF CONTAINMENT, YEARS (Lift-off Testing Schedule, Containment No. 2)

Schedule to be used orovided:

a. The containments are loentical in all aspects such as size, tendon system, design, materials of construction, and method of construction.

The tendon system for Unit 2 does not provide for detensioning.

i Detensioning can be performed only on the Unit 1 tendon system.

b. The 1 -year inspection for Unit 2 will consist of a visual inspection only.

No lift-off testing will be performed on Unit 2 until the 3-year inspection.

c. There is no unique situation that may subject either contenment to a different potential for structural or tendon deterioration.

! d. The Unit 1 and Unit 2 surveillances may b., perfomied back-to-back to l facilitate detensioning of Unit 1 tendons during the Unit 2 surveillance.

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FIGURE 5.5.6-1 SCHEDULE OF LIFT-OFF TESTING FOR TWO CONTAINMENTS AT A SITE

Encl:sira 4 Vogtle Electric Generating Plant Request to Revise Technical Specifications Prestressed Concrete Containment Tendon Surveillance Program Clean-typed TS Pages l

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mj L TABLE OE CONTENTS'-

Y LIST OF FIGURES

_ 2.1.1 -1 Reactor Core Safety Limits.... ...... ...... .............. ............. ..... ...... .... ......... 2.0-2

3.4.16 Reactor Coolant Dose Equivalent 1-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated

- Thermal Power with the Reactor Coolant Spe::ific Activity > 1 pCi/ gram Dose Equivalent 1-131................................. 3.4.16-4 3.7.18-1 Vogtle Unit 1 Burnup Credit Requirements for

. All Cell Storage . . . .. . . . .. .. . . .. . . .. .. . ... . . . .. . . . . . . . .. . . ... . ....... . .... .. . . . . .. . .. .. . . .. .. 3.7.18-3

- 3.7.18 Vogtle Unit 2 Burnup Credit Requirements for-L All Cell Storage . . . . . . . . . . .. . .. . . ... . .. . . . . . . . . .... . . .. . . . .. . . . .. .. . . . .... . . . . . . . . . . . . . .. . .. . 3.7.18-4 4.3.1 Vogtle Unit 1 Burnup Credit Requirements for out-of-4 Storage . . ... . .... .. .. . . . . . . ... .. ... .. . ... . .. . . . . .. . . . . . .. . ... . .. . . . . . .. . . .. . . . 4.0-6 4.3.1 Vogtle Unit 2 Burnup Credit Requirements for 3 -out-of-4 Storage . . . . . . . . . . . .. . . . .... . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . .... ... .. . . . .... . . . . 4.0-7 4.3.1-3 ' Vogtle Unit 2 Burnup Credit Requirements for 3x3 Storage......................................................................................... 4.0-8 4.3.1-4 Vogtle Ur!!s 1 and 2 Empty Cell Checkerboard Storage Configurations ............... ....... . ........ ....... ....................... . 4.0-9

4.3.1 - Vogtle Unit 2 3x3 Checkerboard Storage Configuration ....................... 4.0-10 4.3.1-6 . Vogtle Unitt.,1 and 2 Interface Requirements

- (All Cell to Checkerboard Storage) ............................................... 4.0 11 4.3.1-7 Vogtle Units 1 and 2 Interface Requirements (Checkerboard Storage interface) ................................................ 4.0-12 4.3.1-8 Vogtle Unit 2 Interface Requirements (3x3 Checkerboard to All Cell Storage).............. .......................... 4.0-13 4.3.1-9 Vogtle Unit 2 Interface Requirements

. (3x3 to Empty Cell Checkerboard Storage)................................... 4.0-14 5.5.6-1 Schedule of Litt Off Testing for Two. i Containments at a Site ..................... .................... .. . ................. ... 5.5-22 1 l nAvogTS&B\TS-Toc. doc '

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Vogtle Units 1 and 2 vi Amendment No. (Unit 1)

Amendment No. (Unit 2)

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, Programs and Manuals L{, 5.5 l-5.5 Prograros and Manuals

- 5.5.6 - Prestressed Concrete Containment Tendon Surveillance Proaram - l This program provides controls for monitoring any tendon degradation in prestressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Regulatory Guide 1.35, Revision 2,1976, with the following i exceptions: 1

1. Number of Tendons Detensioned - Only one vertical and one horizontal l tendon are detensioned on Unit 1 each time lift-offs are performed on Unit  !

l 1 per figure 5.5.6-1. Only one vertical or one horizontal tendon is detensioned on Unit 1 each time lift-offs are performed on Unit 2 per figure l 5.5.6-1.

2. Concrete inspection - The concrete adjacent to the vertical tendons
cannot be inspected due to steel plating covering the concrete.

l- 3. The areas adjacent to the tendons are inspected during the tendon t

surveillance instead of during the ILRT.

l Only the Unit 1 containment is subject to the complete surveillance program.

Unit 1 is equipped with selected tendons specifically designed for detensioning. ,

The Unit 2 containment has permanent anchorage assemblies .

(nondetensionable).

i . . l The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon l Surveillance Program inspection frequencies.

.5.5.7 Reactor Coolant Pumo Flywheel Insoection Proaram l This program shall provide for the inspection of each reactor coolant pump flywheel at least once per 10 years by conducting either:

a. An in-place ultrasonic examination ovet the volume from the inner bore of the flywheel to the circle of one-half the outer radius; or c
b. A surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the disassembled flywheel.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Reactor Coolant l

' Pump Flywheel Inspection Program.

(continued)

. Vogtle Units 1' and 2 5.5-5 Amendment No. (Unit 1)

Amendment No. (Unit 2) l

E Programs and Manuals

.i 5.5

' 5.5 Programs and Manuals 5.5.8 Inservice Testino Prooram

. This program provides controls for inservice testing of ASME Code Class 1,2, and 3 components. The program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable- Required Frequencies for

, Addenda terminolcgy for performing inservice

' inservice testino activities testino activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per S2 days Semlannually or every - At least once per 184 days

6 months
Every 9 months At taast once per 276 days -

! Yearly or annua!Iy At least once per 366 days l Biennially or every 2 years At least once per 731 days f

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(continued)

Vogtle Units 1 and 2 5.5-6 Amendment No. (Unit 1)

Amendment No. (Unit 2) a

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Sample Size Criteria

. 4% 2%

01 3 15 25 35 I

Time After Initial Structural Integrity Testing of Containment, Years (Lift-Off Testing Schedu!e, Containment No.1) l 0 35 15 25 35 Time After initial Structural Integrity Testing of Containment, Years (Lift-Off Testing Schedule, Containment No. 2) i Schedule to be used provided:

a. The containments are identical in all aspects such as size, l tendon system, design, materials of construction, and i method of construction. The tendon system for Unit 2 does not provide for detensioning. Detensioning can be performed only on the Unit 1 tendon system.
b. The 1-year inspection for Unit 2 will consist of a visual inspection only. No lift-off testing will be performed en Unit 2 until the 3-year inspection.
c. There is no unique situation that may subject either containment to a different potential for structural or tendon i deterioration.
d. The Unit 1 and Unit 2 surveillances may be performed back-to-back to facilitate detensioning of Unit 1 tendons during the j Unit 2 surveillance. i Figure 5.5.6-1 Schedule of Lift-Off Testing for Two Containments at a Site ,

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. Vogtle Units 1 and 2

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5.5-22 Amendment No. (Unit 1)

Amendment No. (Unit 2)

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