Text

Proposed Tech Specs Reflecting Deletion of 3/4.6.1.5 & Addition of Administration Controls Section 6.2.F.6, Requiring That ISI Program for Post Tensioning Tendons Be Established,Implemented & Maintained,Per RG 1.35,Rev 3
	ML20056G366
Person / Time
Site:	LaSalle
Issue date:	08/20/1993
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20056G358	List: ML20056G357; ML20056G366;
References
	RTR-REGGD-01.035, RTR-REGGD-1.035 NUDOCS 9309030046
	Download: ML20056G366 (72)
	v • d • e

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ATTACHVENT_B l

PROPOSED CHANGES TO THE UCENSE/ TECHNICAL SPECIFICATIONS NPF-11 NPF-18 Vil Vil XIV XIV XXII XXII 1

XXill 3/46-1 3/46-1 3/46-8 3/46-8 3/46-9 3/46-9 3/4 6-10 3/4 6-10 3/4 6-11 3/4 6-11 3/4 6-12 3/4 6-12 3/4 6-13 i

3/4 6-12a 3/4 6-14 3/4 6-12b 3/4 6-15 B 3/4 6-1 B 3/4 6-1 B 3/4 6-2 B 3/4 6-2 6-9 6-9' 1 6-29 6-10 I 6-21' 6-20 i

! 6-22 6-21' i insert Pages 6-22 !

Insert Pages i

These pages are provided for information only, no changes.

k:\nla\dresden\ tendons wpm 9309030046 93082o 5

{DR ADDCK 05000373 7 PDR

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS t

SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS I 3/4.6.1 PRIMARY CONTAINMENT P rimary Contai nme nt Integri ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-1 .

Primary Containment Leakage................................. 3/4 6-2 Primary Contai nment Ai r Loc ks. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-5 MSIV Leakage Control 5ystem................................. 3/4 6-7 h Primary Containment Structural Integrity. . . . . . . . . . . . . . . . . . . . 3/4 6-8 I

Drywell and Suppression Chamber Internal Pressure. . . . . . . . . . . 3/4 6-13 Drywell Average Air Temperature............................. 3/4 6-14 Drywell and Suppression Chamber Purge System................ 3/4 6-15 3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber......................................... 3/4 6-16 Suppression Pool Spray...................................... 3/4 6-20 .

Suppression Pool Cooling.................................... 3/4 6-21 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES........................ 3/4 6-22 :

t 3/4.6.4 VACUUM RELIEF............................................... 3/4 6-35 3/4.6.6 SECONDARY CONTAINMENT Secondary Containment Integri ty. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-37 Secondary containment Automatic Isolation Dampers........... 3/4 6-38 Standby Gas Treatment System................................ 3/4 6-40 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Drywell and Suppression Chamber Hydrogen Recombiner ,

Systems................................................... 3/4 6-43 Drywell and Suppression Chamber Oxygen Concentration.. . . .... 3/4 6-44 5

LA SALLE - UNIT 1 VII ,

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INDEX BASES >

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i SECTION PAGE i 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 and 3/4.5.2 ECCS-OPERATING and SHUTDOWN................. B 3/4 5-1 3/4.5.3 SUPPRESSION CHAMBER..................................... B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity........................... B 3/4 6-1 Primary Containment Leak 1ge. . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 Primary Contai nment Ai r Locks. . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-1 MSIV Leakage Control System............................. B 3/4 6-1 "

\ Primary Containment Structu*al Integrity. . . . . . . . . . . . . . . . B '/t S-2 , '

Drywell and Suppression Chamaer Internal Pressure....... B 3/4 6-2 Drywell Average Ai r Temperature. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-2 Drywell and Suppression Chamber Purge System. . . . . . . . . . . . B 3/4 6-2 3/4.6.2 DEPRESSURIZATION SYSTEMS................................ B 3/4 6-3 ,

3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES.................... B 3/4 6-4 3/4.6.4 VACUUM RELIEF........................................... B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT................................... B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL.................. B 3/4 6-5 LA SALLE - UNIT 1 XIV

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i INDEX LIST OF TABQS (Coritinued)

TABLE PAGE !

4.3.7.3-1 METEOROLOGICAL MONITORING INSTRUMENTATION ,

SURVEILLANCE REQUIREMENTS ......................... 3/4 3-65 3.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION ........ 3/4 3-67 4.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......................... 3/4 3-68 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION ............... 3/4 3-70 t 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION :

SURVEILLANCE REQUIREMENTS ......................... 3/4 3-71 ;

3.3.7.9-1 FIRE DETECTION INSTRUMENTATION ........ ........... 3/4 3-76 :

3.3.7.11-1 EXPLOSIVE GAS MONITORING I

INSTRUMENTATION ................................... 3/4 3-83 4.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......... 3/4 3-84 3.3.8-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM l' ACTUATION INSTRUMENTATION ......................... 3/4 3-87 3.3.8-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM l ACTUATION INSTRUMENTATION SETPOINTS ............... 3/4 3-88 4.3.8.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION i INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......... 3/4 3-89 j 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES .. 3/4 4-9 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS ........... 3/4 4-12

4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM ............................. .... 3/4 4-15 '

4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM l WITHDRAWAL SCHEDULE ............................... 3/4 4-19 k4.6.1.5-1 TENDON SURVEILLANCE ............................... 3/46-I{

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LA SALLE - UNIT (D XXII Amendment No. 85 l

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t INDEX i LIST OF TABLES-(Continued) ,_

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TABLE PAGE o !

t 4.6.1.5-2 TENDON LIFT-OFF FORCE ' . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-12 !

3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES .............. 3/4 6-24 '

3.6.5.2-1 SECONDAP.Y CONTAINMENT YENTILATION SYSTEM i AUTOMATIC ISOLATION DAMPERS ....................... 3/4 6-39 !

3.7.5.2-1 DELUGE AND SPRINKLER SYSTEMS ...................... 3/4 7-16 3.7.5.4-1 FIRE HOSE STATIONS ................................ 3/4 7-19 i 3.7.7-1 AREA TEMPERATURE MONITORING ....................... 3/4 7-25 )

i 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE .................... 3/4 8-7b !

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4.8.2.3.2-1 BATTERY SURVEILLANCE REQUIREMENTS ................. 3/4 8-18 !

3.8.3.3-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD l PROTECTION ........................................- 3/4 8-27 r i

B3/4.4.6-1 REACTOR VESSEL TOUGHNESS .......................... B 3/4 4-6 !

5.7.1-1 COMPONENT CYCLIC OR TRANSIENT LIMITS .............. 5-6 f I

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f LA SALLE - UNIT 1 XXIII Amendment No. 25, 87 l'

l J l 3/4.6 CONTAINMENT SYSTEMS ;

3/4.6.1 PRIMARY CONTAINMENT ,

PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION ;

3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained. '

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2,* and 3. ;

ACTION:

Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in

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COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ;

SURVEILLANCE REQUIREMENTS !

4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:

a. After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A l or B test, by leak rate testing the seal with gas at Pa, 39.6 psig, !

and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 La. l

b. At least once per 31 days by verifying that all primary containment penetrations ** not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in position, except as provided in Table

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f 3p ) 3.6.3-1 of Specification 3.6.3. ,

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g c. By verifying each primary containment air lock OPERABLE per g; Specification 3.6.1.3.

3 9 l 1 d. By verifying the suppression chamber OPERABLE per Specification 3.6.2.1.

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See Special Test Exception 3.10.1

- Except valves, blind flanges, and deactivated automatic valves which are !

located inside the containment, and are locked, sealed or otherwise secured ';

in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed when the primary containment has not been deinerted since the last verification or more often than once per 92 days.

LA SALLE - UNIT 1 3/4 6-1 Amendment No. 5B l

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INSERT A 4.6.1.1.e Verify primary containment structural integrity in accordan with the Inservi Inspection Program for Post Tensioning Tendons. Be i frequency shall be in accordan with the Inservi inspection Program l for Post Tensioning Tendons.

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l k\nla\dresden\ tendons wpf2

_ - - _ _ _ _ - _____ _ - - - _______ _~

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K NCONTAINMENT SYSTEMS j

PRIMARY CONTAINMENT STRUCTURAL INTEGRITY y' x .

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LIMITING CONDITION FOR OPERATION

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3.6.1.5 The structu'ral integrity of the primary containmenty 11 be maintained at a level consistent with the acceptance criteria in SpecT1 cation 4.6.1.5.

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OPERATIONAL C0 DITIONS 1, 2, and 3.

APPLICABILITY: l ACTION:

a. With more than one tendon wit.hsan obseved lift-off force between the predicted lower limit and 90%Afsthe predicted lower limit or with one tendon below 90% of theiredic' tad lower limit, restore the tendon (s) tothe require,ddevel of int'bgrity within 15 days and perform an engineering evaluation of the containmqnt and provide a Special ,

Report to the Commi(sion within 30 days inNccordance with Specifi-cation 6.6C. or te in at least HOT STANDBY wit (in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHDTDOWN within the following 30 hodt .

b. With ar3y/other abnormal degradation of the structura Yntegrity at a levePbelow the acceptance criteria of Specification 4. . 5, restore the' containment vessel to the required level of integrity ithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and perform an engineering evaluation of the contain t ,

/and provide accordance a Special with Report Specification tointhe 6.6C. or be Commission at least HOT STANDBY within 15 d within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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3/4.(c,l.5 INTENT!cNALLV LEFT BLAtJK

[h CE $ 3/4 6 - 9 PM0Q Gr] 3/d 6 -12. DELET6D

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LA SALLE - UNIT 1 3/4 6-8 Amendment No. 18-

DELETE ElG( k bbb 9

\N CONTAINMENT SYSTEMS

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/ 5 SURVEILLANCE REOUIREMENTS /

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'4,.6.1.5 Primary Containment Tendons. The primary containment structural inj.e/ g-rit.y shall be demonstrated at the end of 1, 3 and 5 years after the initia1 l r

stiuctural integrity test (ISIT) and every 5 years thereafter in accordance,/

with\Table 4.6.1.5-1. The structural integrity shall be demonstrated byl i N

a. Determining that a representative sample of at least 13 tendons,,/8 hori- ,

zont'al s and 5 vertical, selected in accordance with Table 4.6.V5-1 have a lift-of,f force equal to or greater than the minimum values listed in Table 4'6.1.5-2 at the first year inspection. Forsubsequedtinspections, '

for tendo'ns and periodicities per Table 4.6.1.5-1, the mimmum lift-off l forcesshal(bedecreasedbytheamountX2logt/ot I "/V tendons and Y2 log t/ to f'o hoop tendons where t is the time interval in years from initialtensio(ingofthetendontothecurrenttestingdateandtois n

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the time interval in years from initial tensionipg/ of the tendon to the s

first inspection and is s equal to 2 years and thd values X1, X2, Y1 and Y2 are in accordance with.the values listed in Table 4.6.1.5-2 for the surveil-s lance tendon. This test shall include esseptially a ccmplete detensioning '

of tendons selected in a'ccordance with Table 4.6.1.5-1 in which the tendon is detensioned to determin's if any wires 4r strands are broken or damaged.

Tendons found acceptable duhng this tesI,t shall be retensioned to their :

J observed lift-off force, t 3f.N During'retensioning of these tendons, the l change in load and elongation shall de j measur,ed simultaneously at a minimum of three, approximately equally hp, aced, levels of force between the seating force and zero. If elongation cptresponding to a specific load differs by more than 5% from that recorded /durigg installation of tendons, an investi-gation should be made to ensu,re that such difference is not related to wire '

failures or slip of wires in' anchorages \ If the lift off force of any one ;

tendon in the total sample / population lies, between the predicted lower limit and 90% of the predicted f fower limit, two tendons, one on each side of this tendon, shall be checked for their lift off If both these adjacent -

li tendonsarefoundacceptable,thesurveillan%orce. cAprogram may proceed con- i

. sidering the single deficiency f as unique and ac'teptable. The tendon (s)

, ' shall be restored,to the required level of integ'rity. More than one tendon ;

le population or the below lift-offthe predicted bounds out of the original samm\of the prescribed low force limit is eviden,dfceaof selected abnormal tendon lying below degradation of the90%

cont'hinment structure. l

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b. \

Performingetendon detensioning and material tests and inspections of a i each group, previous)y hoop ar)d V,stressed tendon that and determining wireover or strand fromlength the entire one tendon of t 'o(he removed wire or strand that: '

/ l 1./ The tendon wires or strands are free of corrosion, cracks and damage.

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/2. Aminimumtensilestrengthvalueof240ksi,theguaranteedu\ ltimate :

/ strength of the tendon material, for at least three wire or strahd 1

/ samples, one from each end and one at mid-length, cut from each re' moved I

/ wire or strand. Failure of any one of the wire or strand samples to

,/ meettheminimumtensilestrengthtestisevidenceofabnormaldegraha-

/ tion of the primary containment structure.

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- LA SALLE - UNIT 1 3/4 6-9 Amendment No. 26 1

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T?ELETE EtJ T(i?E PA 6: TL , ;

k CONTAINMENT SYSTEMS

'\ ' SURVEILLANCE REQUIREMENTS (Continued) / ,

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c. \ Performing a visual inspection of the following: i

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l\ Primary Containment Surfaces - The structural integrity of the exposed N accessible interior and exterior surfaces of the primary containment

\shall be determined during the shutdown for, and prior to, eact$ Type !

As containment leakage rate test by a visual inspection of tt)ese sur-f acys and verifying no apparent changes in appearance or ottier abnormal ;

degra,dation, e.g., widespread cracking, spalling and/or grease leakage.

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End Anchorages - The structural integrity of the end an'chorages, e.g.,

2.

bearing ' plates, stressing washers, shims, wedges and/anchorheads, of all tendohs inspected pursuant to Specification 4.6fl.5a shall be demonstrated,by inspection that no apparent changes have occurred in the visual appearance of the end anchorage.

3. Concrete Surfa s - The structural integrity /of the concrete surfaces '

adjacent to the $nchorages of tendons inspected pursuant to Specifi-cation 4.6.1.5a sh'h{l be demonstrated by visual examination of the l crack patterns to ver fy no abnormal material behavior,

d. VerifyingtheOPERABILITYohthesheathing/ filler grease by the following: ,

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1. No significant voids, i.e., in excess at 5% of the net duct volume, !

i or the presence of free wat'ar wit'hin the grease filler material, ;

taking into account temperature' variations. q

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2. No significant changes havefoccurred in the physical appearance of the sheathing filler greap. /

3. Minimum grease coverage' xists for di ferent parts of the anchorage ;

system. /

4. Chemical properties /are within the tolerance limits specified by the sheathingfiller,esreasemanufacturer. l

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/ LA SALLE - UNIT 1 3/4 6-10

DELETE EMm RE PA 6t'z TABLE 4.6.1.5-1

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\ . TENDON SURVEILLANCE

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\x TENDON NUMBERS

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Years Aft'er Initial St' ructural IntegrityTe's$ 1 3 5 10 15 i Type of Inspectipn H V H V H V H V j ! H V !

48AC 48AC 15C I Visual Inspection y48AC 15C 48AC 15C 48AC 15C }5'C of End Anchorages 56CB 15A 2CB 6C 3BA 28A 4BA /30B 50CB 19A Adjacent Concrete 12CB 20A 14AC 17A 12BA 23A 22A 53BA 13B 41CB/

Surface and Pre- 70B 47C 24BA 32C 21CB 5B 50,AC 57AC stress Monitor- 20CB \ 29A 37CB 42C 23BA 31C /

ing Tests ICB \ 47CB 38CB /

12AC \ 57CB 49AC

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56BA \' 60B 68B 21AC

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Detensioning and 20CB 47C 2CB 42C 23Bp/ 31C 4BA 22A 50CB 19A Material Tests X / c

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TENDON NUMBERS

,/ N Years After / \

Initial Structural 20 /25 \ 30

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35 40 Integrity Test /

Type of Inspection H V,/ H V H \ H V H V 48AC 15C 48AC 15C

\ 15C 48AC 15C i Visual Inspection 48AC /15C of End Anchorages 39CBf 25B 1BA 3B 48CB 7B \(48AC 9CB 25A 36CB 13A 27B Adjacent Concrete 49BA 11A 47AC 12A 51AC IBA 51BA 18B 48BA Surface and Pre- 71D 57BA 58BA Ss0 69D

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stress Monitor-ing Tests [ \

Detensioningand 49BA 11A 47AC 38 48CB 18A SIBA 18E 36CB 13A l l MaterialTes)4 s l

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LA SALLE - UNIT 1 3/4 6-11 Amendment No. 18

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VELET6 E N TiR GI fA (b6 ,/

TABLE 4.6.1.5-2

\ TENDON LIFT-OFF FORCE

\ V TENDONS

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Tendon \ First Year

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Number ' Ends Maximum (kips) Minimum (kips) X1

)(2 :

V15C AN N/A 654.95 N/A / 4.369 B x N/A N/A N/A / N/A +

V28A A '\ N/A 650.53 N/A/ 4.270 :

8 \ N/A N/A N/A N/A V23A A N/A 650.53 N/A 4.270 B \ N/A N/A /N/A N/A 4.270 V5B A N/A 653.27 N/A B '\N/A N/A / N/A N/A 4.369 V31C A N/A 651.90 / N/A B N/A N/A / N/A N/A V30B A N/AN 655.74 / N/A 4.270 B N/A X N/A / N/A N/A V22A A N/A N 655.74 N/A 4.270 B N/A \ N/A N/A N/A V19A A N/A NN 650.53 N/A 4.270 B N/A / N/A N/A N/A l V13B A N/A N / 653.27 N/A 4.270 B N/A \/ N/A N/A N/A V25B A N/A A 653.23 N/A 4.263 8 N/A /\ N/A N/A N/A V11A A N/A- / N650.49 N/A 4.263 8 N/A / \ N/A N/A N/A -

V3B A N/A -/ 653.27 N/A 4.270 -

B N/A / N'/A N/A N/A i V12A A N/A / 650.53 N/A 4.270 B N/A / N/A \ N/A N/A V78 A N/A' 653.27 \ N/A 4.270 i B N/A N/A \ N/A N/A V18A A / N/A 650.53 \ N/A 4.270 B / N/A N/A \ N/A N/A V25A A / N/A 650.53 \ N/A 4.270 B / N/A N/A \ N/A N/A V188 A / N/A 653.27 1/A 4.270 B / N/A N/A N/A N/A V13A A / N/A 643.28 4.263 B/ N/A N/A N/A,\

N/A N/A V278 A' N/A 653.23 N/A _N 4.263

/B N/A N/A N/A \ N/A i "First/ nspection

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LA SALLE - UNIT 1 3/4 6-12 cpJD \

AmendmentIy

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e, D EL E.T6 E.NT( #6 FA (s t-Table 4.6.1.5-2 (Continued) g/

\ s TENDON LIFT-OFF FORCE HOOP TENDONS

's First Year * ;

Tend'on Maximum (kips) Minimum (kips)

Number \ Ends Y1 7 Y2 48AC

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A N/A 647.00 N/A 4.500 Bx N/A 647.00 N/A 4.500 3BA AN N/A 656.46 N/A 4.226 B \ N/A 656.46 N'/A 4.226 12BA A N N/A 637.48 / N/A 6.173 B \ N/A 637.48 / N/A 6.173 N/A 637.48 / N/A 6.173 21CB A 8

\\ N/A 637.48 / N/A 6.173 6.173 23BA A B

N/A

'\N/A 629.71 629.71 631.76 /

!' N/A N/A N/A 6.173 5.437 38CB A N/A B N/A 631.76/ N/A 5.437 49AC A N/A\ 647.00 N/A 4.500 B N/A \ 647f00 N/A 4.500 68B A N/A N 655.39 N/A 4.332 i B N/A \ /655.39 N/A 4.332 N/A 651.16 N/A 4.226 4BA A \s p/ 651.16 N/A 4.226 8 N/A -

41CB A N/A N/

s 644.51 N/A 4.975 B N/A A 644.51 N/A 4.975 50AC A N/A ,/ \ 650.35 N/A 4.500 B N/A / \ 650.35 N/A 4.500 li N/A N/A 4.500 50CB A / N650.35 '

B N/A / 650.35 N/A 4.500 649,.82 N/A 4.538 53BA A N/A /

N/A/ 649}82 N/A 4.538 B

57AC A N/A 650.14 N/A 4.862 B N/A 650.14 \ N/A 4.862 39CB A ,e N/A 644.69 N/A 5.437 B / N/A 644.69 s N/A 5.437 49BA A -

N/A 647.00 \ N/A 4.500 B -

N/A 647.00 N N/A 4.500 71D A N/A 645.20 \ N/A 4.332 B / N/A 645.20 N N/A 4.332 1BA A - N/A 655.82 NN/A 3.914 B/ N/A 655.82 'N/A 3.914 47AC A N/A 644.51 4.975

'B N/A 644.51 N/g\

N/A 4.975 57BA / A N/A 650.18 N/A \ N4.862 B N/A 650.18 N/A 4.862 48CB A N/A 646.48 N/A N4.507 B N/A 646.48 N/A h507

,51AC A N/A 653.75 N/A 4.5Q7 B N/A 653.75 N/A 4.501

' N j/ *First Inspection

,/ LA SALLE - UNIT 1 3/4 6-12a Amendment 1

DE L ET tE ErdT ! CE ('ft G b' p

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\N /a Table 4.6.1.5-2 (Continued) p N

'N x,

TENDON LIFT-OFF FORCE HOOP TENDONS /,/ 4

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N / l First Year

e Tend'on p Numberx Ends Maximum (kips) Minimum (kips) Y1 Y,2' 58BA \A N/A 640.84 N/A /4.912 '

Bs N/A 640.84 N/A / 4.912 !

49CB N/A 639.80 4.500 I AB

'Nx N/A 639.80 N/Af N/A 4.500 SlBA A N '

N/A 653.76 N/A 4.500 B

N/A 653.76 N/A 4.500 59D A N N/A 638.18 / N/A 4.906 !

B

\ N/A 638.18 ,/ N/A 4.906 36CB A x N/A 644.69 ' N/A 5.437

, B 'N/A 644.69 / N/A 5.437 48BA A N/A 653.76 N/A 4.500 l 8 N/A. 653.76 ,/ N/A 4.500

, 69D A N/A 'N 642.31' N/A 4.332

! B N/A N 642.31 N/A 4.332 I N /

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j/ LA SALLE - UNIT 1 3/4 6-12b gj )

Amendmt.ntt i

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.Lw 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 PRIMARY CONTAINMENT INTEGRITY PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restric-tion, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

Y 3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE The limitations on primary containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the ,

accident analyses at the peak accident pressure of 39.6 psig, P . As an addedconservatism,themeasuredoverallintegratedleakagerat8isfurther '

limited to less than or equal to 0.75 L during performance of the periodic tests to account for possible degradati8n of the containment leakage barriers between leakage tests.

Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J to 10 CFR 50 with the exception of exemption (s) granted for main steam isolation valve leak testing and testing the airlocks after each opening.

3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the primary containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the primary containment leakage rate given in Specifications 3.6.1.1 and 3.6.1.2. The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation. Only one closed door in each air lock is required to maintain the integrity of the containment.

3/4.6.1.4 MSIV LEAKAGE CONTROL SYSTEM Calculated doses resulting from the maximum leakage allowance for the '

main steamline isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines provided the main steam line system from the isolation valves up to and including the turbine condenser remains intact. Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously.

The requirement for the leakage control system will reduce the untreated leakage from the isolation valves when isolation of the primary system and containment is required. '

1 LA SALLE - UNIT 1 B 3/4 6-1 P

INSERT B The structural integrity of the primary containment is ensured by the successful completion of the Inservice inspection Program for Post Tensioning Tendons and by associated visual inspections of the stel liner and penetrations for eviden of deterioration or breach of integrity. This ensures that the structural integrity of the primary containment will be maintained in accordance with the provisions of the Primary Containment Tendon Surveillance Program. Testing and Frequency are consistent with the recommendations of Regulatory Guide 1.35, Revision 3, except that the Unit 1 and 2 primary containments shall be treated as twin containments even though the Initial Structural Integrity Tests were not within 2 years of each other.

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CONTAINMENT SYSTEMS BASES q

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3/4.6.1.5 IPRIMARY CONTAINMENT STRUCTURAL INTEC Q Y,_ -

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Tx IhirTiihitHtiWensures tharthe sTructura17ntF#rity of the contliiinment / >

wlQ be maintained comparable to the original design standards for the life of/ '

the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 45 psig in the event of a LOCA. Jhe measurement'o( containment tendon lift off force, the tensile tests of-the t tendon wires or's rands, the visual examination of tendons, anchorages and exposed interior a {nd exterior surfaces of the containment, the,Ahemical and s

visual examination of'tbe sheathing filler grease, and the vpe A leakage test are sufficient to demonstrate this capability.

N The surveillance requirentents for demonstrating he primary containment's structural integrity and the metfi 4 0f predictingihe pre-stress loses are in compliance with the recommendations cfs Regulat6ry Guide 1.35.1, " Inservice Inspection of Ungrouted Tendons in Prestrasiied Concrete Containment Structures,",

January 1976, and proposed RegulatoryJcide'L 35.1, " Determining Prestressing Forces for Inspection of Prestressed' Concrete Con'tainment St'ructures,"

April 1979 with the following cJdification: the tRsted lift-off force of individual tendon tension shall be greater than or equal \

to the initial pre-stress minus the loses [as predicted in the as-built design, which occur between the initial pye' operational structural integrity teliltsand the time of subsequent surveillance.

The require Special Reports from any engineering evaluation or antain-ment abnormafities shall include a description of the tendon condition,'the condition'of the concrete (especially at tendon anchorages), the inspectio'n x proced'ure, the tolerances on cracking, the results of the engineering evalua- K

,ti~n, o and the corrective action taken. N 3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The limitations on drywell and suppression chamber internal pressure ensure that the containment peak pres <sure of 39.6 psig does not exceed the design pressura of 45 psig during LOCA conditions or that the external pres-sure differential does not exceed the design maximum external pressure differen-tial of 5 psid. The limit of 2.0 psig for initial positive primary containment pressure will . limit the total pressure to 39.6 psig which is less than the design pressure and is consistent with the accident analysis. i 3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the ;

containment peak air temperature does not exceed the design temperature of 340 F during LOCA conditions and is consistent with the accident analysis. ;

3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM i The drywell and suppression chamber purge supply and exhaust isolation !

valves are required to be closed during plant operation except as required for inerting, de-inerting and pressure control. These valves have been demonstrated capable of closing during a LOCA or steam line break accident from the full open position.

LA SALLE UNIT 1 8 3/4 6-2 Amendment t. H

l I

ADMINISTRATIVE CONTROLS Onsite Review and Inverticative Function (Continued)

b. Responsibility The Onsite Review and Investigative Function shall be responsible for conducting the following: ,

1) Review of all applicable plant Administrative Procedures recommended in Appendix A of Reg Guide 1.33, Revision 2, February 1978 and changes thereto;

2) Review of Emergency Operating Procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33 and

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\ changes thereto;

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\ 3) Review of all proposed tests and experiments that affect r

%) nuclear safety;

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\ 4) Review of all proposed changes or modifications to plant

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systems or equipment that affect nuclear safety;

{[gu- 5) Review of proposed changes to the Fire Protection Program;

6) Review of the Station Security Plan and submittal of recommended (l

( 3 changes to the station Security Plan in accordance with station procedures; y r1 )

k, Q 7) Review of Emergency Plan and identification of recomended j changes;

( 3

) 8) Review of changes to the PROCESS CONTROL PROGRAM and the

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OFFSITE DOSE CALCULATION MANUAL;

9) Review of all proposed changes to the Technical Specifications k]H4

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or Operating License, and any proposed change which involves an unreviewed safety question that is to be submitted to the fqim) Comission for approval;

[ q / 10) Review of investigation results for all violations of the Technical Specifications, including the preparation and

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E forwarding of reports covering evaluations and recommendation

\ fp to prevent recurrence;

11) Review of investigation results for all REPORTABLE EVENTS and k /

other significant operating abnormalities including the

/ T +E; preparation and forwarding of reports covering evaluations and recommendation to prevent recurrence.

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j h 121 Review of investigation results for any accidental, unplanned, or uncontrolled radioactive release including the preparation

(( c2e *)} / and forwarding of reports covering evaluations and recommendations to prevent recurrence; t to ,T

13) Review of Unit operations to detect potential hazards to (A7) nuclear safety;

14) Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the Offsite 7

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N Review and Investigative Functiong! r.1 9"3 ,

LA SALLE UNIT 1 6-9 Amendment No. 75. 86

i i

i ADMINISTRATIVE CONTROLS i

PLANT OPERATING PROCEDURES AND PROGRAMS (Continued) i

1. Limitations on the annual and quarterly doses to a MEMBER OF THE '

PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous i' effluents released from each unit to areas beyond the SITE BOUND- ,

ARY confoming to Appendix I to 10 CFR Part 50, ,

j. Limitations on venting and purging of the containment through ;

the Primary Containment Vent and Purge System or Standby Gas Treatment System to maintain releases as low as reasonably .[

achievable, ,

k. Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation !

from uranium fuel cycle sources conforming to 40 CFR Part 190. ;

5. Radiological Environmental Monitoring Program l A program shall be provided to monitor the radiation and radionuclides l in the environs of the plant. The program shall provide (1) represen-tative' measurements of radioactivity in the highest potential exposure :

pathways, and (2) verification of the accuracy of the effluent monitor- ,

ing program and modeling of environmental exposure pathways. .The 4 program shall (1) be contained in the ODCM, (2) conform to the guid- ;

ance of Appendix I to 10 CFR Part 50, and (3) include the following: i

a. Monitoring, sampling, analysis, and reporting of radiation and ,

radionuclides in the environment in accordance with the method-ology and parameters in the ODCH, l

b. A Land Use Census to ensure that changes in the use of areas at *

[m>3 (h and beyond the SITE BOUNDARY are identified and that modifications !

to the monitoring program are made if required by the results of i

( this census, and i Participation in a Interlaboratory Comparison Program to ensure (v3W c. ,

that independent checks on the precision and accuracy of the (d

L measurements of radioactive materials in environet.ntal sample matrices are performed as part of the quality assurdact. program for cavironmental monitoring.

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6. 3 ACTION TO BE 1Miti IN THE EVENT OF A REPORTABLE EVENT IN ILt (

OPERATION The following actions shall be taken for REPORTABLE EVENTS

a. The Commission shall be notified and a Licensee Event Report ~

i submitted pursuant to the requirements of Section 50.73 to 10 CFP. Part 50, and

b. Each REPORTABLE EVENT shall be reviewed pursuant to Specifi-cation 6.1.G.2.c(1).

LA SALLE UNIT 1 6-20 Amendment No. 55, SE, 86 l

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INSERT C 6.2.F.6 Inservice inspection Program for Post Tensioning Tendons This program provides controls for monitoring any tendon degradation in pre-stressed 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 3,1989, except that the unit 1 and 2 primary containments shall be treated as twin containments even though the initial Structural Integrity Tests were not within 2 years of each other.

The provisions of 4.0.2 and 4.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

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TO J CHA%E5 'n ADMINISTRATIVE CONTROLS N J 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down immediately pur-suant to Specification 2.1.1, 2.1.2 and 2.1.3, and critical reactor operation shall not be resumed until authorized by the NRC. The conditions of shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate. The incident shall be reviewed pursuant to Specifications 6.1.G.1.a and 6.1.G.2.a and a separate Licensee Event Report for each occurrence shall be l prepared in accordance with Section 50.73 to 10 CFR Part 50. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President BWR Operations and the Manager of Offsite Review and Investigative Function shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6.5 PLANT OPERATING RECORDS A. Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least 5 years:

1. Records of normal plant operation, including power levels and periods of operation at each power level;

2. Records of principal maintenance and activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety;

3. Records and reports of reportable events;

4. Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4 of these specifications) are being met. All equipment failing to meet surveil-lance requirements and the corrective action taken shall be recorded;

5. Records of changes to operating procedures; G. Shift engineers' logs; and 7 Byproduct material inventory records and source leak test results.

B. T rords and/or logs relative to the following items shall be rwarded in manner convenient for review and shall be retained for the 'ife of the Wt: .

1. Substitution or replacement of principal items of equipment pertain- i ing to nuclear safety; j

2. Changes made to the plant as it is described in the SAR;

3. Records of new and spent fuel inventory and assembly histories;

4. Updated, corrected, and as-built drawings of the plant; LA SALLE UNIT 1 6-21 Amendment No. 66. EE. 86

ADMINISTRATIVE CONTROLS PLANT OPERATING RECORDS (Continued)

5. Records of plant radiation and contamination surveys;

6. Records of offsite environmental monitoring surveys; .

7. Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant, in accordance with 10 CFR Part 20;

8. Records of radioactivity in liquid and gaseous wastes released to the environment;

9. Records of transient or operational cycling for those components that have been designed to operate safety for a limited number of transient or operational cycles (identified in Table 5.7.1-1);

10. Records of individual staff members indicating qualifications, .

experience, training, and retraining; i

11. Inservice inspections of the reactor coolant system;

12. Minutes of meetings and results of reviews and audits performed by the offsite and onsite review and audit functions;

13. Records of reactor tests and experiments;

14. Records of Quality Assurance activities required by the QA Manual, except for those items specified in Section 6.5.A;

15. Records of reviews performeJ for changes made to procedures on equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59;

16. Records of the service lives of all hydraulic and mechanical snubbers i required by specification 3.7.9 including the date at which the ser- l vice life commences and asssciated installation and maintenance records; j

17. Records of analyses requi- J by the radiological environmental !

monitoring program; And a -

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18. Records of reviews perfore J for changes made to the 0FFSITE f DOSE {

CALCULATION MANUAL and the PECESS CONTROL PROGRAM.,v

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,..q 6.6 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted

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LA SALLE UNIT 1 6-22 Amendment No. SE,86 l

INDEX ;

.i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS j 3/4.6.1 PRIMARY CONTAINMENT ,

i Primary Containment Integrity............................... 3/4 6-1 Prima ry Contai nment Lea kage. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-2 i Primary Containment Air Locks............................... 3/4 6-5 '

MSIV Leakage Control System................................. 3/4 6-7 i

\ Prima ry Containment Structural Integrity. . . . . . . . . . . . . . . . . . . . 3/4 6-8 E Drywell and Suppression Chamber Internal Pressure........... 3/4 6-16 j D rywell Average Ai r Temperature. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-17 Drywell and Suppression Chamber Purge System................ 3/4 6-18 3/4.6.2 DEPRESSURIZATION SYSTEMS Suppression Chamber......................................... 3/4 6-19 l 1

Suppression Pool Spray...................................... 3/4 6-23 t Suppression Pool Cooling.................................... 3/4 6-24 i

3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES......................... 3/4 6-25 i

3/4.6.4 VACUUM RELIEF............................................... 3/4 6-38 i

3/4.6.5 SECONDARY CONTAINMENT ,

Secondary Containment Integrity.............................. 3/4 6-40 -

Secondary Containment Automatic Isolation Dampers........... 3/4 6-41 i

Standby Gas Treatment System................................ 3/4 6-43 :

i 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL !

l Drywell and Suppression Chamber Hydrogen Recombiner Systems................................................... 3/4 6-46 Drywell and Suppression Chamber Oxygen Concentration........ 3/4 6-47 LA SALLE - UNIT 2 VII .

1 I

INDEX l l

BASES i

)

i SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS !

3/4.5.1 and 3/4.5.2 ECCS-OPERATING and SHUTDOWN................. B 3/4 5-l' '

i 3/4.5.3 SUPPRESSION CHAMBER..................................... B 3/4 5-2 l 3/4.6 CONTAIRMENT SYSTEMS $

1 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity........................... B 3/4 6-1 Primary Containment Leakage... ......................... B 3/4 6-1

\

Primary Containment Air Locks........................... B 3/4 6-1

~

^ l MSIV Leakage Control System.............................

B 3/4 6-1 .

{ Primary Containment Structural Integrity. . . . . . . . . . . . . . . . B 3/4 6-2 ' I Drywell and Suppression Chamber Internal Pressure....... B 3/4 6-2 i

D rywel l Average Ai r Temperature. . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 6-2 Drywell and Suppression Chamber Purge System............ B 3/4 6-2 l

3/4.6.2 DEPRESSURIZATION SYSTEMS................................ B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES.................... B 3/4 6-4 l 3/4.6.4 VACUUM RELIEF........................................... B 3/4 6-4 ,

3/4.6.5 i SECONDARY CONTAINMENT.......... ........................ B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTR0L.................. B 3/4 6-5 e

i i

LA SALLE - UNIT 2 XIV i

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LIST OF TABLES (Continued)

TABLE PAGE ;

3.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION ........ 3/4 3-67 i 4.3.7.4-1 REMOTE SHUTDOWN MONITORING INSTRUMENTATION i SURVEILLANCE REQUIREMENTS ......................... 3/4 3-68 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION ............... 3/4 3-70 '

4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION .

SURVEILLANCE REQUIREMENTS ......................... 3/4 3-71 3.3.7.9-1 FIRE DETECTION INSTRUMENTATION .................... 3/4 3-76 3.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION .......... 3/4 3-83 4.3.7.11-1 EXPLOSIVE GAS MONITORING INSTRUMENTATION :

SURVEILLANCE REQUIREMENTS ......................... 3/4 3-84 (

3.3.8-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION ......................... 3/4 3-87 3.3.8-2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS ............... 3/4 3-88 :

i 4.3.8.1-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS ......... 3/4 3-89 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES .. 3/4 4-10 3.4.4-1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS ........... 3/4 4-13 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND [

ANALYSIS PROGRAM .................................. 3/4 4-16 ;

4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM ;

WITHDRAWAL SCHEDULE ............................... 3/4 4-20 i 4.6.1.5-1 TENDON SURVEILLANCE ............................... 3/4 6-11

( 4.6.1.5-2 TENDON LIFT-0FF FORCE ............................. 3/4 6-12 l 1

3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES .............. 3/4 6-27 LA SALLE - UNIT 2 XXII Amendment No. 69

l 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT 1

PRIMARY CONTAINMENT INTEGRITY ,

LIMITING CONDITION FOR OPERATION i

3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained. '

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2,* and 3. I ACTION:

Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . '

SURVEILLANCE REQUIREMENTS ,

~

4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:

a. After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened following Type A or B test, by leak rate testing the seal with gas at Pa, 39.6 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d for all other Type B and C penetrations, the r combined leakage rate is less than or equal to 0.60 La.

b. At least once per 31 days by verifying that all primary containment

.e penetrations ** not capable of being closed by OPERABLE containment

/ automatic isolation valves and required to be closed during accident j g, ) conditions are closed by valves, blind flanges, or deactivated

{ \ automatic valves secured in position, except as provided in Table b .

(W 1 3.6.3-1 of Specification 3.6.3. l (h

fg c. By verifying each primary containment air lock OPERABLE per Specification 3.6.1.3.

>- d. By verifying the suppression chamber OPERABLE per Specification M 3.6.2.1. '

See Special Test Exception 3.10.1

- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment, and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed when the primary containment has not been deinerted since the last verification or more often than once per 92 days.

LA SALLE - UNIT 2 3/4 6-1 Amendment No. 41

LNSERT A .

t 4.6.1.1.e Verify primary containment structural integrity in accordance with the Inservice Inspection Program for Post Tensioning Tendons. The ,

frequency shall be in accordance with the Inservice inspection Program for Post Tensioning Tendons. ;

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CONTAINMENT SYSTEMS

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PRIMARY CONTAINMENT STRUCTURAL INTEGRITY !

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LIMITING CONDITION FOR OPERATION w

3.6.1.5 The . structural integrity of the primary containment shall be,m/aintained at a level cohsistent with the acceptance criteria in Specification 4'.6.1.5.

\ /

APPLICABILITY: ERAT 10NAL CONDITIONS 1, 2, and 3. /

b*

d ACTION:

\

? a. With more thag one tendon with an observed lift-off force between the predicted lowe limit and 90% of the predicted Jdwer limit or with one tendon belo 0% of the predicted lower limit, restore the tendon (s) to the re dithin 15 days and

,7 perform an engineer' quired level i g evaluation of of theintegrity'tainment con and provide a Special Report to th Commission within 30' days in accordance with '

/yd Specification 6.6C. or e in at least H T' STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

bi I

iij b. With any other abnormal deg

\ dationg/ f the structural integrity at

/o a level below the acceptance riteria of Specification 4.6.1.5, restore the containment vesset N to/the required level of integrity 2

g J - , within72hoursandperformanehgineeringevaluationofthecontain-C dj ment and provide a Special Repdrt to the Commission within 15 days he in accordance with Specificat' ion 6. C. or be in at least HOT STANDBY L J* within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and'in COLD {iUTDOWNwithinthefollowing

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30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . j/

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va i h O! SURVEILLANCE REOUIREMENTS i

oeg y/ +- ) 4.6.1.5 Primary Containmen Tendons. The primary conta ent structural b integrity shall be demonstrated at the end of 1, 3, and 5 ears after the l 5

t; d i initialstructuralinteditytest(ISIT)andevery5yearsthereafterin The structural integrity shh11 be demon-

[g 5 c+i accordance with Table 4.6.1.5-1.

strated by:

g kbiM a. Determi ing that a representative sample of at least 13 endons, 8

( o ,@[i e

horiz dtal and 5 vertical, selected in accordance with Tab e 4.6.1.5-1 hav lift-off force equal to or greater than the minimum lues listed

\,

hD in able 4.6.1.5-2 at the first inspection. For subsequent f4 tendons and periodicities per Table 4.6.1.5-1, the minimum lift-off spections, forces shall be decreased by the amount X2 log t/t for V tend s and

/Y2logt/t for hoop from initi31 tendons tensioning of where t is the the tendon time to the 18terval current in year testing date d t is the time interval in years from initial tensioning of the ten t8 the first inspection and is equal to 4 years. The values X1, X2, Y1, and Y2 are in accordance with the values listed in Table 4.6.1.5-2 for the surveillance tendon. This test shall include essentially a -

y LA SALLE - UNIT 2 3/4 6-8 Amendment No.14

_ _ _ _ . _ m . _ _ _ __ _ _ .._ - - ___ _

l W LETE ENTtE PA G r 5 l

i

/ I CONTAINMENT SYSTEMS

/ l' NSURVEILLANCE RE0VIREMENTS (Continued) l

\ f complete detensioning of tendons selected in accordance with !

stable 4.6.1.5-1 in which the tendon is detensioned to determine J 1

hny wires or strands are broken or dawaced. Tendons faund acceptable !

during this test shall be retensioned to their observed lift stf !

forle , 1 3%. Duringretensioningofthesetendons,thechapfein !

i load'and s elongation shall be measured simultaneously at a pinimum of three,'approximately equally spaced, levels of force betw4en the l seat.ing fprce and zero. If elongation corresponding to/a specific j j

' load differs by more than 5% from that recorded during installation i oftendons,Naninvestigationshouldbemadetoensur,e'thatsuch difference iss not related to wire f ailures or slipfof wires in .l anchorages. I'fs the lift-off force of any one ter; don in the total ,

sample populatiot) lies between the predicted lower limit and 90% of !

the predicted low'er limit, two tendons, one orv'each sidd of this j tendon, shall be checked for their lift-off force. If both these i adjacent tendons are\found acceptable, the,(urveillance progrsm may !

j proceed considering the single deficiency /as unique and acceptMe :

The tendon (s) shall be bestored to the required level of inter,rity. ('

Morethanonetendonbeloy{thepredicte,dboundsoutoftheorigin sample population or the 11 t-off force of a selected tendon lying ;

below 90% of the prescribed iower ljmit is evidence of abnormal ,

degradation of the containmen sty 0cture. j i

i

b. Performing tendon detensioning,s (i material tests and inspections of l j- a previously stressed tendon, wire Nr strand from one tendon of each f group, hoop and V, and determining i at over the entire lenoth of '

the removed wire or strand/ that:

/

The tendon wires of strands are fre of corrosion, cracks and ;

r 1.

damage. / l i /

1 2. Aminimumterys'ilestrengthvalueof240(si,theguaranteed i j ultimate strength of the tendon material,\for at least three

l wire or st/and samples, one from each end aqd one at mid-length, cut from/each removed wire or strand. Failurse of any one of

! the wird or strand samples to meet the minimuEt tensile strength :

test)sevidenceofabnormaldegradationofthe\ rimary contain- ,

.f men. structure. l

c. Perfording a visual inspection of the following:

1. Primary Containment Surfaces - The structural integrity'of the exposed accessible interior and exterior surfaces of the rimary

/

containment shall be determined during the shutdown for, dnd

/ prior to, each Type A containment leakage rate test by a vihyal j inspection of these surfaces and verifying no apparent changet f.

/ in appearance or other abnormal degradation, e.g., widespread

/ cracking, spalling, and/or grease leakage.

t s'

/

/ LA SALLE - UNIT 2 3/4 6-9

. = _ . - .

CNT /l b f0AG E

. . EL66 h

W l

/ '

l CONTAINMENT SYSTEMS j

, SURVEILLANCE REOUIREMENTS (Continued) l l

j l

End Anchorages - The structural integrity of the end anchorages, l 2.

! e.g. , bearing plates, stressing washers, shims, wedges, and/nchor- l heads, of all tendons inspected pursuant to Specification,4.6.1.5a.

shall be demonstrated by inspection that no appa.,:7+ changes t

\haveoccurredinthevisualappearanceoftheendsncaor' age. !

\ / i 1 3. toncrete Surfaces - The structural integrity of the, concrete l

.s faces adjacent to the anchorages of tendons inspected pursuant ;

to etification 4.6.1.5a. shall be demonstrated

natict) of the crack patterns to verify no abnorma,by l material visual exam behavih . .

d. Verifying the a ERABILITY of the sheathing fill e grease by the i following.

1. No significan voids, i.e., in excess 5% of the net duct

?

volume, or the p esence of free wate ithin the grease filler g

l material, taking nto account temp ature variations. i

/' No significant chang.s have occurred in the physical appearance l

2. ^

of the sheathing fill r grease / ;

/

3. Minimum grease coverage i fs for different parts of the i anchorage system. f l 1

4. Chemical properties are with the tolerance limits specified l i

by the sheathing fillef grease anufacturer. :

/ :

/

/ i

/ ;

l

/

4 I

1 1

l

DELETE EN Tt RE~ [M GE

'\ TABLE 4.6.1.5-1

/ !

TENDON SURVEILLANCE TENDON NUMBERS .

[~ l Years After \ / '

Initial Structbral 10 15- :

Integrity Test \ 1 3 5 Typeof-Inspection \ H V H. V H V H ji H V Visual Inspection 48EG 215C 48EG 215C 48EG 215C 48EG' 215C 48EG - 215C f of End Anchorages 56GF' 215A 2GF 206C 3FE 228A ,4FE 230B 50GF 219A Adjacent Concentrate 2GF 220A 14EG 217A 12FE 223A 1GF 222A- 53FE 213B :

Surface and Pre- TOF 247C 37GF 242C 21GF 205B SOEG 57EG

. stress Monitor- 20GE 229A 47GF 232C 23FE 231 i

ing Tests 1G 57GF 38GF '

12EG 60F 49EG 24FE 68F :

56FE 0 3FE 231C 4FE 222A 50GF 219A 20GF 247C 2GF 242C nhnhand

'x / 1

[ TENDON NUMBERS f

, Years After 20 25

/ 30 35 40 l

l Initial Structural Integrity Test / ;

Type of Inspection H V/ H V H\ V H V H V Type of Inspection 48EG/215C 48EG 215C 48EG h15C 48EG 215C 48EG 215C f of End Anchorages 39GF 225B 1FE 2038 48GF 2073 49GF 225A 36GF 213A :

Adjacent Concrete 49FE 211A 47EG 212A SIEG 218A 51FE 218B 48FE 227B i Surface,and Pre- 71J 57FE 58FE 59J 69J-stress Monitor-ing Tests je

" "d 49FE 211A 47EG 2038 48GF 218A 51FE 8B 36GF 213A at r t

- 1 LA'SALLE - UNIT.2' 3/4 6-11 c- ~ - -._ - - . -, -.--s

. . + . - , , , . - .

i DE LET C EIV T 1P E PA GC l

~ i t TABLE 4.6.1.5-2

\ TENDON LIFT-OFF FORCE ,

\ V TENDONS

\ .

rs ear * -

j Tendon ;

Number Ends Maximum (kips) Minimum (kips) X1 X2 V215C 'As N.A. 649.14 N.A. }9.302 i B\ N.A. N.A. N. A. / N.A. i V215A A s N.A. 644.85 N.A. '/ 18.865 B \ N.A. N. A. N.A. / N.A. l V220A N.A. 644.85 18.865 A \ N.A. N.A.

N.

N.A.

A/ N.A.

B \

V247C A N N.A. 641.94 JK A.

19.088 B x N.A. N.A. /N. A. N.A. ;

644.85 N.A. 18.865 V229A A B

\N.N.A.

A. N.A. /-

/ N. A. N.A.

V206C A NQ. 649.14 / N.A. 19.302 l B N.A. N.A. / N.A. N. A.

V217A A N.A. 644.85/ N.A. 18.865 N.A.\s B N.A./ N. A. N.A. ;

V232C A N.A. N 4 N.A. 19.302 i B N.A. \ 649[A.

N. N. A. N.A.

V242C A N.A. N f49.14 N.A. 19.032 B N.A. \ / N.A. .N.A. N.A. -

V228A A N.A. 644.85 N.A. 18.865 B N.A. /y' \ N.A. N.A. N.A.

V223A A N.A. / N644.85 N.A. 18.865 B N.A. / N.A N.A. N.A. .

V205B A N.A. /

647w59 N.A. 18.865 '

B N.A. / N.A\ N.A. N.A.

V231C A .

649.14N .N.A. 19.302- ,

B N.Af.

N.A N.A. N N. A. N.A.

V230B A fpA. 647.59 \ N.A. 18.865 ;

B N.A. N.A. \ N. A. N.A. !

V222.A A / N.A. 644.85 \N N.A.

N. A. 18.865 i B / N.A. N.A. N.A. j V219A A /~ N. A. 644.85 'K. A. 18.865.

t B / N. A. N.A. N .V . N.A.

V213B A / N.A. 647.60 N. AA 18.865 B / N.A. N.A. N. A. N N.A.

N.A. 640.38 N.A. \ 18.625 i V225B A/

B, N.A. N.A. N. A. N N.A. l V211A A N.A. 644.82 N.A. N 8.834 B N. A. N.A. N. A. N,A. !

A N.A. 640.41 N.A. 18.456 V203B / N. A. N.A. N.A. N. Ah

/ B

F/stInspection !

l

/

LA SALLE UNIT 2 3/4 6-12

pE LET 6 t=/4 ii RE fAGE >

l l

s TABLE 4.6.1.5-2 (Continued) l' TENDON LIFT-OFF FORCE i V TENDONS ;

.\ :

First Year

l Tendo Number E N nds Maximum (kips) Minimum (kips) X1 f2 i V207B 'A N.A. 647.59 N.A. / 18.865 BN N.A. N.A. N. A. / N. A. i V218A A\ \ N.A. 644.85 N.A./ 18.865 !

B N.A. N.A. N.V N.A. t V225A A \ N.A. 644.85 NfA. 18.865 l B \ N.A. N.A. N.A. N.A. l V218B A N.A. 647.59 / N.A. 18.865

\\ N.A. N.A. / N. A. N.A.

B V213A A ~\ N.A. 644.82 / N.A. 18.834 8 \ N.A. N.A. / N.A. N.A. t V227B A N.A. 647.56 / N.A. 18.8f4 !

B NSA. N. A. / N.A. N.A. l V212A A N. At 637.78 N.A. 18.656 B N.A.\ N.A. N.A. N.A. l i

/

l i

' i 1

.i I

l

/

\

/

Fi!stInspection f LA SALLE - UNIT.2 3/4 6-13 \

DELET6 ENTtR6 (% GE ,

i

/ ;

TABLE 4.6.1.5-2 (Continued) l

\ TENDON L7FT-OFF FORCE

~

\ H00F TENDONS

\ '

N '

First Year

Tendok Maximum (kips) Minimum (kips) Y1 Y2 Number \ Ends ;

N.A. 641.01 N.A. 19~.881 l 48EG 9 641.01 N.A. <19.881 ,

Bx N.A.

N. A. 639.34 N.A. / 21.480 i 56GF A\\

B N.A. 639.34 N.A. / 21.480 '

N.A. 629.27 N. A. / 27.272 12GF A \ N.A/ 27.272 -;

B \ N.A. 629.27 N.A. 643.76 N, A. 19.139 70F A B

Kx N.A. 643.76 N.A. 19.139 27.272 20GF A \ N.A. 621.50 / N.A.

B \ N.A. 621.50 / N.A. 27.272 4 1GF A 1. A. 645.54 / N.A. 18.670 '

B thA. 645.54 / N.A. 18.670 '

A tL A 629.27 N.A. 27.272 12EG '

B N. Ah 629.27 / N.A. 27.272 56FE A N.A. N 639.34 N.A. 21.480 ,

B h.A. N 639/34 N.A. 21.460 l N.A. 648.19 N.A. 18.670 :

2GF A N.A.

NN 648.19 N.A. 18.670 -l B '

A N.A. N / 621.50 N.A. 27.272 14EG B N.A. N/ 621.50 N.A. 27.272 A N.A.

/ \ 629.27 N. A. 27.272 24FE 27,272 ;

B N.A. / \ 629.27 N.A.

A N.A. 618.86 N.A. 23.754- t 37GF j/

B N.A. - 612.86 N.A. 23.754 N. A. 639N5 N.A. 21.980 47GF A / 639.75 N.A. 21.980 B N.A. / ,

A N. A./ 636.15 \ N. A. 21.434 ;

57GF ~

B N. A$ 636.15 \ N.A. 21.434 NA. 640.20 \ N.A. 21.233 60F A B A4. A. 640.20 \ N.A. 21.233 N.A. 650.84 \ N.A. 18.670 3FE A / 650.84 \ N.A. 18.670 B / N.A.

A / N.A. 629.27 N. A. 27.272 ;

12FE 8 / N.A. 629.27 NN. A. 27.272 '

N.A. 629.27 N.A\ 27.272 ,

21GF A / N. A. \ 27.272 ;

B / N.A. 629.27 N. A. 621.50 N.A. \ 27.272 i 23FE A/ 621.50 N.A. \ 27.272 '

B/ N.A.

38GF A N.A. 631.63 N.A. g4.021 1

/B N.A. 631.63 N.A. 24.021 l A N.A. 641.01 N.A. 19x881 !

49EG /

/ B N.A. 641.01 N.A. 19.881 ,

FidtInspection \ ~

l

/ \

LA SALLE - UNIT 2 3/4 6-14 3

7

~

DELET6 E N T@ E' PA G E -

t TABLE 4.6.1.5-2 (Continued)

TENDON LIFT-OFF FORCE y N HOOP TENDONS

\

rst Year * ;

Tendon Number Maximum (kips) Minimum (kips) Y1 j Y2

{nds '

68F A N.A. 642.43 N.A. / 18.927 B\ N.A. 642.43 N.A. / 18.927 '

A N.A. 645.54 N.Af 18.670 4FE \ N.A. 645.54 N.A. 18.670 B \ '

N.A. 637.89 N.A. 21.979 41GF A B

\\ N.A. 637.89 /N. A. 21.979 50EG A \ N.A. 644.37 / N. A. 19.881 >

B \ N.A. 644.37 / N.A. 19.881 19.881 50GF 53FE A

B A

\N. A.

h. A.

N.A.

644.37 644.37 643.78 /

[' N.A.

N.A.

19.881 20.049 B N.Ah 643.78 / N.A. 20.049 57EG A N.A. N 643.67/ N.A. 21.480 i B N.A. \ 643.67 N.A. 21.480 39GF A N.A. N 63E 46 N.A. 24.021 ,

B N.A. N 637.46 N.A. 24.021 ?

N.A. j641.01 N.A. 19,881 49FE A N N.A. 19.881 B N.A. \ / 641.01 71J A N.A. V' 646.67 N.A. 19.138 :

B N.A. A_ 646.67 N.A. 19.138 1FE A N.A. / \ 650.61 N.A. 17.292 B N.A. / N650.61 N.A. 17.292 47EG A N.A. ,/ 647.89 N.A. 21.980 s 8 N.A. / 637.89 N.A. 21.980 ;

57FE A / 64392 N.A. .21.480 l B N.A./

N. A. 643.71 N. A. 21.480 l 48GF A N.@ 647.75 \ N.A. 19.912 B N.A. 647.75 \ N.A. 19.912 SIEG A N.A. 647.75 N N.A. 19.912 .

B / N. A. 647.75 \ N.A. 19.912 l 58FE A / N.A. 634.30 \N N.A. 21.701 !

B / N.A. 634.30 N.A. 21.701- l 49GF A / N.A. 641.01 \ N.A. 19.881 ;

B / N.A. 641.01 \N.A. 19.881 SlfE N.A. 647.77 A. 19.881 j A / N.A. 647.77 N... 19.881 B/ ,

59J A' N.A. 638.83 N. A\. 21.676 !

/B -N.A. 638.83 N.A. \ 21.676 ,

36GF rA N.A. 637.46 N.A. \ 24.021

/

f B N.A. 637.46 N.A. \24.021 ,

48FE / A N.A. 647.77 N. A. l'.881 i I

/ B N.A. 647.77 N.A. 1 .881 69J A N.A. 643.76 N.A, 19.1Q8

/ B N.A. 643.76 N.A. 19.13

/

j/ *First Inspection

[ LA SALLE - UNIT 2 3/4 6-15 \

o l

[ N(ww~ ECT 3/4.6 CONTAINMENT SYSTEMS l BASES i 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 PRIMARY CONTAINMENT INTEGRITY PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restric- i tion, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions. ,

A.

3/4.6.1.2 PRIMARY CONTAINMENT LEAKAGE The limitations on primary containment leakage rates ensure that the ;

total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of 39.6 psig, P . As an .

adjed conservatism, the measured overall integrated leakage rat $ is further limit (d to less than or equal to 0.75 L during performance of the periodic i tests to tccount for possible degradati8n of the containment leakage barriers between led age tests.

Operating experience with the main steam line isolation valves has indicated that degradation has occasionally occurred in the leak tightness of.

the valves; therefore the special requirement for testing these valves. t The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J to 10 CFR 50 with the exception of exemption (s) granted for main steam isolation valve leak testing and testing i the airlocks af ter each opening.

j 3/4.6.1.3 PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the primary containment air ,

locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY !

and the primary containment leakage rate given in Specifications 3.6.1.1 and ;

3.6.1.2. The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured ,

position during reactor operation. Only one closed door in each air lock is .

. required to taaintain the integrity of the containment. l 3/4.6.1.4 MSIV LEAKAGE CONTROL SYSTEM l Calculated doses resulting from the maximum leakage allowance for the '

main steamline isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines provided the main steam line i system from the isolation valves up to and including the turbine condenser <

t remains intact. Operating experience has indicated that degradation has ;

occasionally occurred in the leak tightness of the MSIV's such that the specified leakage requirements have not always been maintained continuously.

The requirement for the leakage control system will reduce the untreated s leakage from the isolation valves when isolation,of the primary system and containment is required. ,

LA SALLE - UNIT 2 B 3/4 6-1 i

INSERT B he structural integrity of the primary containrnent is ensured by the successful completion of the Inservi inspection Program for Post Tensioning Tendons and by associated visual inspections of the steel liner and penetrations for eviden of deterioration or breach of integrity. Bis ensures that the structural integrity of the ,

primary containment will be maintained in accordan with the provisions of the Primary Containment Tendon Surveillance Program. Testing and Frequency are consistent with the reconirendations of Regulatory Guide 1.35, Revision 3, except that the Unit 1 and 2 primary containments shall be treated as twin containrnents even though the initial Structural Integrity Tests were not within 2 years of each other.

l 4

l k:\nla\dresden\ tendons wpf6 .

l 4

l CONTAINMENT SYSTEMS BASES -

, /

/ p 3/4.6.1.5 LERIMARYl0NTAIMENLSTRUCIURAllNTEGRIIYMvQLC

\ wil(beThis limitation ensures that the structural integrity of the containment /

j maintained comparable to the original design standards for the life off the f$cility.

s Structural integrity is required to ensure that the containpetst will withstand the maximum pressure of 45 psig in the event of a LOCA. ,.The measurement s'of containment tendon lif t-off force, the tensile tests,,of the c orages and tendon wires or strands, the visual examination of tendons, an) chemical and exposed interior andsexterior surfaces of the containment, t)e visual examination of'the sheathing filler grease, and the-Type A leakage test are sufficient to demons ate this capability.

The surveillance requirements for demonstrating the primary containment's structural integrity and the metho'dqf predicJiffg the prestress losses are in compliance with the recommendations o bRegulatory Guide 1.35, " Inservice Inspection of Ungrouted Tendons in Prestfessed Concrete Containment Structures," l January 1976, and proposed Regulat ,ory' Guide h 35.1, " Determining Prestressing Forces for Inspection of Prestrested Concrete CBntainment Structures," April 1979 with the following clar,ification: the testedl i t-off force of individual tendon tension shall be greater than or equal to the { initial prestress minus the losses, as predic,ted in the as-built design, which ocBu between the initial pre-operational structural integrity test and the time of su(bst uent surveillance.

Therequirs(SpecialReportsfromanyengineeringevaluationb ontain-ment abnormalities shall include a description of the tendon conditi he conditioit of the concrete (especially at tendon anchorages), the inspect b proce' dure, the tolerances on cracking, the results of the engineering evalua

,A.fon, and the corrective action taken. ,

3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE ,

The limitations on drywell and suppression chamber internal pressure ensure that the contaihment peak pressure of 39.6 psig does not exceed the design pressure of 45 psig during LOCA conditions or that the external pres-sure differential does not exceed the design maximum external pressure differen-tial of 5 n

The limit of 2.0 psig for initial positive primary containment pressure wies .imit the total pressure to 39.6 psig which is less than the design pressure and is consistent with the safety analysis.

3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 340*F during LOCA conditions and is consistent with the safety analysis.

3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM The drywell and suppression chamber purge supply and exhaust isolation valves are required to be closed during plant operation except as required-for inerting, de-inerting and pressure control. These valves have been demonstrated capable of closing during a LOCA or steam line break accident from the full open position. l i

LA SALLE UNIT 2 B 3/4 6-2 Amendment No. 25

7 /J O Ch'6 E5 ADMINISTRATIVE CONTROLS MY OW Y

Onsite Review and Investigative Function (Continued) comprehensive interdisciplinary review coverage under this function; (4) independently review and approve the findings and recommendations i developed by personnel performing the Onsite Review and Investigative 8 Function; (5) report all findings of noncompliance with NRC require-ments, and provide recommendations; and (6) submit to the Offsite Review and Investigative Function for concurrence in a timely manner, those items described in Specification 6.1.G.1.a which have been approved by the Onsite Review and Investigative Function.

b. Responsibility The Onsite Review and Investigative Function shall be responsible for conducting the following:

1) Review of all applicable plant Administrative Procedures recommended in Appendix A of Reg Guide 1.33, Revision 2, February 1978 and changes thereto;

2) Review of Emergency Operating Procedures required to implement the requirements of NUREG-0737 and Supplement 1 to NUREG-0737 as stated in Section 7.1 of Generic Letter No. 82-33 and changes thereto;

3) Review of all proposed tests and experiments that affect nuclear safety;

4) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety;

5) Review of proposed changes to the Fire Protection Program;

6) Review of the Station Security Plan and submittal of recommended changes to the station Security Plan in accordance with station procedures;

7) Review of Emergency Plan and identification of recommended changes;

8) Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL;

9) Review of all proposed changes to the Technical Specifications or Operating License, and any proposed change which involves an unreviewed safety question that is to be submitted to the Commission for approval;

10) Review of investigation results for all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluations and recommendation to prevent recurrence;

11) Review of investigation results for all REPORTABLE EVENTS and other significant operating abnormalities including the preparation and forwarding of reports covering evaluations and recommendation to prevent recurrence.

LA SALLE - UNIT 2 6-9 Amendment No. 62, 70

ADMINISTRATIVE CONTROLS

12) Review of investigation results for any accidental, unplanned, or uncontrolled radioative release including the preparation and forwarding of reports covering evaluations and recommendations to prevent recurrence;

13) Review of Unit operations to detect potential hazards te ,

nuclear safety; Performance of special reviews and investigations and reports c'

M }s 2

O) 14 A

thereon as requested by the Superintendent of the Offsite Review and Investigative Functionq. A

/

c.

\

Authority Yh v

c._

( The Onsite Review and Investigative Function shall:

( s$ 1 1) Advise the Station Manager on all matters related to Nuclear

) .- Safety; a w ,

f S ~i. 2) Recommend to the Station Manager the disposition of items

( $g considered under Specification 6.1.G.2.b.1) through 9) prior to

\ d b their implementation; (4

. 1 3) Include among its review conclusions for each item considered under Specification 6.1.G.2.b.1) through 4), a determination of j 3 q whether or not the item involves an unreviewed safety question.

g (.

T F)r 4) Provide prompt notification to the Vice-President BWR

,p Operations and the Superintendent of the Offsite Review and

- Investigative Function of disagreement between the Onsite i

k q"M} Review and Investigative Function and the Station Manager. The Station Manager shall follow the recommendations of the Onsite j

(jt y, V y 's J

Review and Investigative Function or select a course of action that is more conservative regarding safe operation of the

'i* facility.

2o (yy $

d. Records

1) Reports, reviews, investigations, and recommendations

( R "f ], prepared and performed for Specification 6.1.G.2a shall be documented and forwarded to the Superintendent of the

(^ Offsite Review and Investigative Function unless otherwise jf

=

specified.

2) Copies of all records and documentation shall be kept on file at the station.

e. Procedures l l Written administrative procedures shall be prepared and main-tained for conduct of the Onsite Review and Investigative Function. These procedures shall include the following: ;

1) Content and method of submission and presentation to the Station Manager, Vice President BWR Operations, and the Superintendent of the Offsite Review and Investigative i Function.

6-10 Amendment No. 52, 70 ;

.LA SALLE - UNIT 2 l

ADMINISTRATIVE CONTROLS PLANT OPERATING PROCEDURES AND PROGRAMS (Continued)

1. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUND-ARY conforming to Appendix I to 10 CFR Part 50,

j. Limitations on venting and purging of the containment through the Primary Containment Vent and Purge System or Standby Gas Treatment System to maintain releases as low as reasonably achievable,

k. Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

5. Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) represen-tative measurements of radioactivity in the highest potential exposure .

pathways, and (2) verification of the accuracy of the effluent monitor- '

ing program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guid-ance of Appendix I to 10 CFR Part 50, and (3) include the following:

a. Monitoring, sampling, analysis, and reporting of radiation and

,m radionuclides in the environment in accordance with the method-(- 1 ology and parameters in the ODCM, (N2p

)

b. A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications

{W to the monitoring program are made if required by the results of g this census, and d) wy

c. Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality asserance program

( for environmental monitoring.

6.3 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT IN PLANT OPERATION 1

The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a Licensee Event Report '

submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and ),

b. Each REPORTABLE EVENT shall be reviewed pursuant to Specifi-cation 6.1.G.2.c(1). j l

l l

LA SALLE - UNIT 2 6-20 Amendment No. 89, 70

INSERT C 6.2.F.6 Inservi inspection Program for Post Tensioning Tendons This program provides controls for monitoring any tendon degradation i~n pre-stressed 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 Surveillan Program, inspection frequencies, and accepbr.ce criteria shall be in accordan with Regulatory Guide 1.35, Revision 3,1989, ex pt that the unit 1 and 2 primary containments shall t:e treated as twin containments even though the Initial Structural Integrity Tests were not within 2 years of each other.

The provisions of 4.0.2 and 4.0.3 are applicable to the Tendon Surveillan Program inspection frequencies.

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NO CWhd6E p g nJ rc M w W c * /

ADMINISTRATION CONTROLS 6.4 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safety limit is exceeded, the reactor shall be shut down immediately pursuant to Specification 2.1.1, 2.1.2 and 2.1.3, and critical reactor operation shall not be resumed until authorized by the NRC. The conditions of shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate. The incident shall be reviewed pursuant to Specifications 6.1.G.l.a and 6.1.G.2.a and a separate Licensee Event Report for each occurrence shall be prepared in accordance with Section 50.73 to 10 CFR Part 50. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President BWR Operations and the Manager of Off-site Review and Investigative Function shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

6.5 PLANT OPERATING RECORDS A. Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least 5 years:

1. Recoros of normal plant cperation, including power levels and periods of operation at each power level;

2. Records of principal maintenance and activities, including inspection and repair, regarding principal items of equipment pertaining to nuclear safety;

3. Records and reports of reportable events; +

4. Records and periodic checks, inspection and/or calibrations performed to verify that the surveillance requirements (see Section 4 of these specifications) are being met. All equipment failing to meet surveil-lance requirements and the corrective action taken shall be recorded;

5. Records of changes to operating procedures;

6. Shift engineers' logs; and

7. Byproduct material inventory records and source leak test results.

B. Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the plant:

1. Substitution or replacement of principal items of equipment pertain-ing to nuclear safety;

2. Changes made to the plant as it is described in the SAR;

3. Records of new and spent fuel inventory and assembly histories;

4. Updated, corrected, and as-built drawings of the plant;

5. Records of plant radiation and contamination surveys;

6. Records of offsite environmental monitoring surveys;

7. Records of radiation exposure for all plant personnel, including all ,

contractors and visitors to the plant, in accordance with 10 CFR Part 20;

8. Records of radioactivity in liquid and gaseous wastes released to '

the environment, LA SALLE - UNIT 2 6-21 Amendment No. S , 70

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ADMINISTRATION CONTROLS PLANT OPERATING RECORDS (Continued) l

9. Records of transient or operational cycling for those components that have been designed to operate safety for a limited number of transient or operational cycles (identified in Table 5.7.1-1);

10. Records of individual staff members indicating qualifications, experience, training, and retraining;

11. Inservice inspections of the reactor coolant system;

12. Minutes of meetings and results of reviews and audits performed by the offsite and onsite review and audit functions;

13. Records of reactor tests and experiments;

14. Recorc;s of Quality Assurance activities required by the QA Manual, except for those items specified in Section 6.5.A;

15. Records of reviews performed for changes made to procedures on equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59;

16. Records of the service lives of all hydraulic and mechanical snubbers >

required by Specification 3.7.9 including the date at which the service life commences and associated installation and maintenance records;

17. Records of analyses re monitoring program;V@ quired by the radiological ,j, environmental 18.

Recordsofreviewsperformedforchangesmadetothf.e'FFSITEDOSE CALCULATION MANUAL and the PROCESS CONTROL PROGR ', i 6.6 REPORTING REQUIREMENTS ih In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted 7 to the director of the appropriate Regional Office of Inspection and Enforce- -

ment unless otherwise noted.

A. Routine Reports

1. Startup Report A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) instr.11ation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) ;

modifications that may have significantly altered the nuclear, !

thermal, or. hydraulic performance of the plant. The report shall j in general include a description of the measured values of the i operating conditions or characteristics obtained during the test )

program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain i satisfactory operation shall also be described. Any additional l specific details requ, ired in license conditions based on other l commitments shall be included in this report. l LA SALLE - UNIT 2 6-22 Amendment No. U , 70

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ATTACHNENT C SIGNIFICANT HA?ARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specification ,

Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:

The Inservice Inspection of the Primary Containment Tendons will be performed in accordance with the Inservice inspection Program for Post Tensioning Tendons, which will be a program required by Technical Specification Administrative Controls section 6.2, Plant Operating Procedures and Programs. This program in conjunction with specification 3/4.6.1.1 will assure that the primary containment integrity will be maintained throughout the life of the plant for both LaSalle County Station (LaSalle) Unit 1 and Unit 2. The design of the primary containment is not affected by this change and therefore the probability of an accident occurring is not increased; because, neither accident initiators nor accident assumptions are affected by this change.

The consequences of analyzed accidents are not increased, because the integrity of the Primary Containment is maintained through specification 3.6.1.1 and the tendon program required by proposed specification 6.2.F.6.

2) Create the possibility of a new or different kind of accident from any accident previously evaluated because:

The Primary Containment Integrity is assured through continued surveillance and test of the Primary Containrnent Tendons in accordance with the Inservice Inspection Program for Post Tensioning Tendons, which will be a program required by Technical Specification Administrative Controls section 6.2, Plant Operating Procedures and Prograrns. Technical Specification 3/4.6.1.1, Primary Containment integrity, provides appropriate controls and actions related to loss of containment integrity.

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ATTACHNENT C (continued)

3) Involve a significant reduction in the rnargin of safety because:

The Deletion of Technical Specification 3/4.6.1.5 does not reduce the margin of safety, because Primary Containment Integrity is required to be maintained per specification 3.6.1.1, Primary Containment Integrity and proposed addition of Administrative Control 6.2.F.6, inservice Inspection Program for Post Tensioning Tendons.

Guidance has been provided in " Final Procedures and Standards on No Significant Hazards Considerations," Final Rule, 51 FR 7744, for the application of standards to license change requests for determination of the existence of significant hazards considerations. This document provides examples of amendments which are and are not considered li'K ely to involve significant hazards considerations. Rese proposed amendments most closely fit the example of a change which may either result in some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but where the results of the change are clearly within all acceptable criteria with respect tc the system or component specified in Standard Review Plan section 3.8.1, Concrete Containment.

1 This proposed amendment does not involve a significant relaxation of the criteria used to establish safety linits, a significant relaxation of the bases for the limiting safety

system settings, or a significant relaxation of the bases for the liniting conditions for operations. Therefore, based on the guidance provided in the Federal Register and :

the criteria established in 10 CFR 50.92(c), the proposed change does not constitute a significant hazards consideration.

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ATTACHNENT D !

I ENVIRONNENTAL ASSESSNENT STATENENT APPUCABUTY REVIEW Commonwealth Edison has evaluated the proposed amendrnent against the criteria. !

for identification of licensing and regulatory actions requiring environrnental assessment in accordance with 10 CFR 51.20. It has been determined that the i proposed changes meet the criteria for a categorical exclusion as provided under 10 CFR 51.22(c)(9). This conclusion has been detemnined because the changes ,

requested do not pose significant hazards considerations or do not involve a significant ;

increase in the amounts, and no significant changes in the types, of any effluents that may be released off-site. Additionally, this request does not involve a significant :

increase in ' individual or cumulative occupational radiation exposure. l 4

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ATTACHIVENT_E COMPARISON OF CURRENT TECHNICAL SPECIFICATION REQUIREMENTS TO THE PROPOSED TECHNICAL SPECIFICATION REQUIREMENTS AND THE INSERVICE INSPECTION PROGRAM FOR POST TENSIONING TENDONS

1. The current Limitation and Action 3.6.1.5, 'The stractural integrity of the primary

containment shall be maintained at a level consistent with the acceptance criteria in e l Specification 4.6.1.5," is being deleted.

The current Specification 3.6.1.1 Limitation and Action 3.6.1.1, " PRIMARY CONTAINMENT INTEGRITY shall be maintained," assures structural integrity as

v. ell as the other aspects of Primary Containment operability.

2. The Applicability of specification 3.6.1.5 is the sarne as the Applicability of l specification 3.6.1.1, except for the 3.6.1.1 footnote *, which allows Special Test Exception 3.10.1 for low power physics testing without Primary Containment.

Tendons are part of containment integrity, and therefore are not required during low power physics testing. Therefore, 3.6.1.5 is not required to be listed in a separate specification.

3. The current Specification 3.6.1.5 Actions are being incorporated as is into the inservice inspection Program for Post Tensioning Tendons, with minor changes,

! which include addressing how the actions apply to unit 1 and 2. The actions will be applied to the Unit on which the unacceptable condition is found.

4. The current Technical Specification Surveillance Requirement 4.6.1.5 is being deleted from the Technical Specifications, except for the proposed Surveillance ,

Requirermnt 4.6.1.1.e, which is as follows Verify primary containment structural integrity in accordance vith the Inservice 3

Inspection Program for Post Tensioning Tendons. The freauency shall be in accordance with the Inservice Inspection Program for Post Tensioning Tendons.

5. The program contains and reformats the details of Surveillance Requirerrent 4.6.1.5. The following changes or additions to the Surveillance Requirernents 4.6.1.5 are being made as part of the proposed program and are consistent with i Regulatory Guide 1.35, Revision 3, with the exception to the condition requiring the Unit 1 and 2 Primary Containment ISITs to be performed vdthin 2 years.

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ATTACHNENT E (continued)

P A. To date, complete Isis have been performed for the 1st, 3rd, 5th,10th, and 15th year inspections of Unit 1 and the 1st, 3rd, and 5th year inspections of Unit 2. Wth the current specification, complete Isis will continue every 5 years. The Inservice Inspection Program for Post Tensioning Tendons establishes the frequency of the testing as stated in the Regulatory Guide 1.35, Rev. 3 for a twin unit site:

1) Visual inspection that includes grease sampling will be perfonned on '

each unit at every 5 year interval from the date the initial 5th year testing was completed.

2) Physical testing (i.e., tendons lift off, detensioning, and wire tensile tests) will be performed on each unit at every 10 year interval from the date the initial 5th year testing was cornpleted.

B. Currently, Surveillance Requirement 4.6.1.5.a states:

.. If the lift-off for of any one tendon in the total sample population lies between the predicted lower limit and 90% of the predicted lower linit, two tendons, one on each side of this tendon, shall be checked for their lift-off force. .."

In accordance w;th Regulatory Guide 1.35, Rev. 3, the Inservice Inspection Program for Post Tensioning Tendons has the following slightly less restrictive requirement:

"If the measured prestressing force of a selected tendon in a group lies between 95% of prescribed lower linit and 90% of prescribed lower linit, two additional tendons, one on each side of first tendon, should be checked for their prestressing forces." !

LaSalle is interpreting the term, " prescribed lower limit," to rrean, " predicted lower linit," per Regulatory Guide 1.35, Rev. 3, section B discussion of '

Regulatory Position 7.1 and Regulatory Guide 1.35.1. The term " predicted !

lower limit," will be used in the Inservice Inspection Program for Post Tensioning Tendons and implementing procedures.

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ATTACHNENT E (continued)

C. Currently, Surveillance Requirement 4.6.1.5.c.1 states:

" Primary Containment Surfaces - The structural integrity of the exposed accessible interior and exterior surfaces of the primary containment shall be detemined during the shutdown for, and prior to, each Type A containment leakage rate test by a visual inspection of these surfaces and verifying no apparent changes in appearance or other abnormal degradation, e.g., widespread cracking, spalling and/or grease leakage."

This surveillance nixes two required inspections, one per Regulatory Guide 1.35, Rev. 3, section C.3.1, which is as follows:

"3.1. The exterior surface of the containment should be visually examined to detect areas of large spall, severe scaling, D-cracking in an area of 25 square feet or more, other surface deterioration or disintegration, or grease leakage."

10 CFR 50, Appendix J:

Section Illa 1, requires a Type A test pretest containrnent inspection as follows:

"(a) Containment inspection in accordance with VA shall be performed as a prerequisite to the performance of Type A tests."

Section V.A, Containnunt inspection, requires the following:

"A general inspection of the accessible interior and exterior surfaces of the containment structures and components shall be performed ,

prior to any Type A test to uncover any evidence of structural 1 deterioration which may affect either the containment structural integrity or leak-tightness. If there is evidence of structural deterioration. Type A tests shall not be performed until corrective action is taken in accordance with repair procedures, nondestructive ,

examinations, and tests as specified in the applicable code specified i in @ 50.55a at the commencement of repair work. Such structural !

deterioration and corrective actions taken shall be reported as part of the test report, submitted in accordance vdth V.B."

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ATTACHNENT E (continued)

The exterior inspection required by Regulatory Guide 1.35 is being included in the Inservice inspection Program for Post Tensioning Tendons. The interior add exterior inspection required by 10 CFR 50, App. J will be included in the surveillance procedure for Type A tests.

D. Currently, Surveillance Requirernent 4.6.1.5.c.2 and 3 state:

2. "End Anchorages - The structural integrity of the end anchorages, e.g.,

bearing plates, stressing washers, shims, wedges, and anchorheads, of all tendons inspected pursuant to Specification 4.6.1.5a shall be demonstrated by inspection that no apparent changes have cccurred in the visual appearance of the end anchorage."

3. " Concrete Surfaces - The structural integrity of the concrete surfaces adjacent to the anchorages of tendons inspected pursuant to .

Specification 4.6.1.5a shall be dernonstrated by visual examination of the L crack pattems to verify no abnormal material behavior.

In accordance with Regulatory Guide 1.35, Rev. 3, the Inservice inspection Program for Post Tensioning Tendons has the following slightly less restrictive requirement for visual inspection:

3.2. Tendon anchorage assembly hardware (such as bearing plates, stressing washers, shims, wedges, and buttonheads, of all tendons selected as described in Regulatory Position 2 should be visually examined. For those containments for which only visual inspections need be performed, tendons selected as described in Regulatory Position 2 should be visually examined to the extent practical without dismantling -

load bearing components of the anchorage or removing grease caps.

3.3. Bottom grease caps of all vertical tendons should be visually insoected to detect grease leakage or grease cap deformations.

Removal of the grease caps is not necessary for this inspection.

3.4. Concrete surrounding visually inspected tendon anchorages should .

also be checked visually for indications of abnormal material behavior.

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ATTACHFENT E (continued)

E. Currently, Surveillance Requirement 4.6.1.5.a states:

If elongation corresponding to a specific load differs by more than 5% from that recorded during installation of tendons, an investigation should be made to ensure that such difference is not related to wire failures or slip of wires in anchorages. .. "

in accordance with Regulatory Guide 1.35, Rev. 3, the Inservice inspection Program for Post Tensioning Tendons has the following slightly less restrictive requirement for elongation during retensioning:

7.2 During detensioning and retensioning of tendons, if the elongation corresponding to a specific load differs by more than 10% from that recorded during installation of the tendons, an investigation should be made to ensure that the difference is not related to wire failures or slip of wires in anchorages. A difference of more than 10% should be considered reportable.

6. Unit 1 and 2 tables 4.6.1.5-1, Tendon Surveillance, provide the results of the random selection performed for the tendons requiring inspection and test for each Structural Integrity Test interval. The Unit 1 and 2 Tables are being relocated to the Inservice inspection Program for Post Tensioning" Tendons. A Note is being added to the tables regarding the " type of inspection required for each interval as follows:

As applicable to a twin unit site.

This will allow required inspections to be performed without complicating the tables.

The scope of the inspections at each interval for the tendons specified in the table for that interval will be specified in the program in accordance with Regulatory Guide 1.35, Rev. 3, as discussed in 5.D, above. Regulatory Guide 1.35, Rev. 3, providcs an acceptable method of selection of tendons for future inspections and tests, which will be used, if changes are made to tables 4.6.1.5-1.

7. Unit 1 and 2 tables 4.6.1.5-2, Tendon Uft-off Force, V (vertical) Tendons and Hoop Tendons, are being relocated to the Inservice inspection Program for Post Tensioning Tendons.

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1 APPENDIX A !

JUSTIFICATION FOR EXCEPTION TO REGULATORY. GUIDE 1.35, REV. 3 i i

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July 6, 1993 CHRON #

To: Station Manager LaSalle County Station

SUBJECT:

LaSalle County Station Engineering Work Request E93-101 Post-Tensioning ISI Technical Spec. Revision Safety Related

REFERENCE:

Sargent & Lundy Latter, C.N. Krishnaswamy to J. A. Miller (CECJ), Dated July 1, 1993 (SCS-0447)

Site Engineering and Construction (SEC) has reviewed and approves of the evaluation and justification presented in the above referenced letter. This work was performed to prepare justification to enable Commmonwealth Edison to seek approval from Nuclear Regulatory Commission (NRC) to revise Technical Specification to treat LaSalle station as twin unit site relative to the periodic inservice inspection of the containment post-tensioning system.

The proposed revision will enable LaSalle to limit ensuing '

10th year post-tensioning system ISI of unit 2 to visual inspection only, instead of the current complete physical inspection.

Since work is performed on safety related structure safety evaluation (50.59) has been prepared to justify qualification of ,

LaSalle unit as twin unit in relation to periodic post-tensioning ISI inspections.

If you have any questions regarding this matter, please contact me at site extension 2785.

Mohammad.N. Malik i Site Engin 9ns DAeeri: g M. Dowd Site Engineering l Attachment ;

cc: J. Miller i J. Gieseker M. Dougherty G. Swihart NEDCC

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SARGENT & LUNDY l ENGINEERS -

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( 342 3 389= 4000 S&L Letter No. SCS-0447 !

July 1, 1993 Project No. 9265-101 l

WIN 2157 -

Commonwealth Edison Company LaSalle County Station - Units 1&2 Engineering Work Request (EWR) No. E93-101 Post-Tensioning ISI Technical Specification Revision Modification No.: N/A Safety Code: N/A Safety-Related Mr. J. A. Miller Station Support / Engineering Support Supervisor Commonwealth Edison Company LaSalle County Station R.R. /1, P.O. Box 220 2601 North 21st Road Marseilles, IL 61341

Dear Mr. Miller:

Sargent & Lundy (S&L) has completed the preparation of a justification to enable Commonwealth Edison Company (CECO) to seek approval from the Nuclear Regulatory Commission (NRC) to revise the station technical specifications to treat LaSalle County station as a twin unit site relative to the periodic inservice inspection of the containment post-tensioning system.

This task was performed at the request of Mr. M. Malik of Ceco via Engineering Work Request No. E93-101. ;

The proposed revision, upon approval by the NRC, will permit Ceco to limit the ensuing loth year post-tensioning system ISI of Unit 2 to visual inspection only, instead of the current technical specification requirement of complete physical (i.e.

tendon lift-off, detensioning, and wire tensile tests) and visual inspections of each unit during each of its inspection periods.

Based on the revision, complete ISIS can be alternated between the two units for subsequent inspections. The resulting cost savings is estimated to be over $300,000 for the ensuing 10th year ISI of Unit 2 and over $2,000,000 for the subsequent ISIS to be performed over the remainder of the 40 year operating life of the two units.

SARGENT & LUNDY E PC o i N E E R 3 C M 8CaGO Mr. J. A. Miller July 1, 1993 Commonwealth Edison Company Page 2 l

l The justification for revising the post-tensioning ISI technical specifications is provided in Attachment 1. Supporting documents that were reviewed in detail with Mr. M. i the justification are listed in Attachment 2.Malik ofACECO to prepare marked up copy t

of Table 4.6.1.5-1 of station technical specifications 3/4.6.1.5 is provided in Attactunent 3.

No 101.

S&L drawings are affected by the scope of this EWR No. E93-A draft of this letter has been previously forwarded to Messrs.

M. Dowd and M. Malik of CECO for review and comment per ENC Procedures QE-81 and comments have been addressed.

If you have any questions or need further assistance with \

obtaining NRC approval of the proposed revision, please contact me at (312) 269-6807.

t j

Yours very truly,

% '.duSm '

C. N. Krishnasw y Structural Project Engineer 2

CNK:jh Attachments - All Recipients CECO DDL DC: CO20 Copies:

J. W. Gieseker S. D. Berkman M. Dougherty M. Dowd M. Malik G. Swihart S. Bhaktiari ,

CHRON System i C. H. Furlow / File L. V. Jacques R. A. Parson J. L. Engleman ]

i SC5-044 7.CJK F

a ATTACWENT 1 t

The containment structures for Unit I and Unit 2 of LaSalle County Station t (LSCS) are identical structures at one site. There is no design, i construction, or environmental differences between the two containments. The l containments are identical in all aspects such as size, tendon system, design, materials of construction, and method of construction. There is no unique difference that may subject either containment to a different potential for structural or tendon deterioration. They were constr$cted by the same general contractor in the same manner. Construction cf the two containments was continuous from the start of each containprent and lasted approximately the same period of time from their respective start of construction to completion of post-tensioning installation. ,

Unit 1 post-tensioning was completed in July 1978 and Unit 2 post-tensioning was completed in December 1980. The Unit 1 Structural Integrity Test (SIT) was perfomed in December 1978. At that time, Unit 2 SIT was intended to be completed in December 1980. It was also intended to initiate inservice inspection (ISI) of the containment post-tensioning system in accordance with :

Regulatory Guide (RG) 1.35, Revision 2 January 1976 which, for a twin unit site such as LSCS, allows that the second containment structure need only be visually inspected.

t 0 wing to the additional requirements to accommodate the suppression pool '

hydrodynamic loading, construction was (identically) extended for both Unit I <

and Unit 2 and operating license (OL) for Unit I was granted in April 1982 and for Unit 2 in December 1983. The Unit 2 SIT was successfully completed earlier in June 1983, approximately 4) years from Unit 1 SIT.

During this period, proposed Revision 3 to RG 1.35 was published in April 1979 :

which required complete ISI (i.e. tendon lift-off, detensioning, wire tensile !

tests, and visual inspection of anchorage components and filler grease inspection) for each unit in two containment sites if the containment SITS were not performed within two years of each other.

In deference to the proposed Revision 3 of RG 1.35 requirements, LSCS technical specifications for containment post-tensioning ISI voluntarily comitted to performing complete physical and visual inspections for each containment. To date, complete ISIS have been performed for the 1st, 3rd, 5th,10th, and 15th year inspections of Unit I and the 1st, 3rd, and 5th year inspections of Unit 2. The identical post-tensioning systems and containments of the two units have successfully met the acceptance criteria specified for each of the ISIS performed to date.

Results of these extensive ISIS (relative to the tendon stress level after due concrete creep and shrinkage and wire relaxation losses, wire condition and ultimate tensile strength, containment concrete condition, condition of the concrete around the end anchorages, condition of the end anchorage components, and the condition of the casing filler grease) clearly demonstrate that the performance of Unit 2 SIT more than two years after Unit 1 SIT is not at all a factor contributing to any unique behavior that may subject either containment to a different potential for structural or tendon deterioration. Results of the SIT of the two containment structures also demonstrated that their

ATTAttMENT 1 (continued) structural responses under test pressure were practically identical even though Unit 2 SIT was performed 4% years after Unit 1 SIT. In addition, the integrated leak rate tests (ILRT) of the two containments were successfully performed within a one year span, in July 1982 for Unit I and July 1983 for Unit 2.

Based on this actual perfomance record and in consideration that the period of active concrete creep and shrinkage is nearly over, we conclude that alternating complete ISIS between the two units for the remainder of the plant life is justifiable. The 15th year complete ISI was performed for Unit I during its December 1992 outage. Therefore, it is sufficient to perform only visual inspection and filler grease inspection for the 10th year ISI of Unit 2 during its planned September 1993 outage.

Table 4.6.1.5-1 of LSCS Unit I and Unit 2 technical specification 3/4.6.1.5 for containment post-tensioning system surveillance requirements have been marked up accordingly for NRC approval.

1

ATTACm ENT 2 i

1. USNRC Regulatory Guide 1.35, Revision 2, January 1976. l

2. USNRC Regulatory Guide 1.35, Revision 3, July 1990.

3. LSCS-UFSAR Section 3.8.1.7.3.1, Revision 0, April 1984.

4. LSCS Units 1 and 2 Technical Specifications 4.6,1.5, Surveillance Requirements for Primary Containment Structural Integrity.

5. LSCS Unit 1 Cor.tainment Post-Tensioning System ISI Reports.

6. LSCS Unit 2 Containment Post-Tensioning System ISI Reports.

7. LSCS Unit I Containment. Structural Integrity Test Report.

8. LSCS Unit 2 Containment Structural Integrity Test Report.

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TABLE 4.6.1.5-1 TENDON SURVEILLANCE TENDON NUMBERS Years After iInitial Structural l In* _grity Test 1 3 5 10 15 TypeofInspectioM H V H V H V H Y H V I visual Inspection 48AC 15C 48AC 15C 48AC 15C 48AC 15C 48AC of End Anchorages 56CB 15A 15C ;

2CB GC 3BA 2BA 4BA 30B Adjacent Concrete 50CB 19A 12CB 20A 14AC 17A 12BA 22A 41CB 22A 53BA 138 surface ant

Pre- 708 47C 24BA 32C 21CB stress Monitor-EB 50AC 57AC 20CB 29A 37CB 42C 23BA ing Tests 31C 1CB 47CB 3BCB 12AC 57CB 49AC 56BA 60B 6SB 21AC 1octensioning and 20CB 47C 2CB 42C 23BA 31C 4BA 22A 50CB 19A

. Material Tests t-l TENDON NUMBERS Years After

, Initial Structural 20 25 30 35

' Integrity Test 40 Type of InspectierM H '

V H Y H V lH Y H V Visual Inspection 48AC 15C 48AC 15C 48AC 15C 48AC of End Anchorages 39CB 15C 48AC 15C 258 1BA 3B 48CB 78 Adjacent Concrete 49CB 25A 36CB 13A 49BA 11A 47AC 12A 51AC IBA 51BA 1BB 4BBA 27B Surface and Pre' 71D 57BA SBBA stress Monitor- ESD 690 ing Tests l

Detensioning and 49BA 12A 47AC 38 48CB 18A 51BA 188 36CB 13A Material Tests iR As applicek to a ' twin unib sN LA SALLE - UNIT 1 3/4 6-11 Amencment No. 1B l

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- TBERNI 1RSEERE -

Years After Initial Stnactural Istagrity Test. 1 3 5 3 15 Type of Inspection $ N Y N Y N Y ~N V N V I

Visus! Inspectfas' 6 215C 4M B 213C er Ens Amunerages 4e 213C 6 ZUC M IIRC {

Adjacent cancrete -

5E E 2154 2 r 2DIC 3PE 225A 4FE 23 5 SO F 213A St efper ans etw=

12F 2254 16 227A 12FE 2234 41 F 222A SEPE 2135 7W 22 27 F 24EC 23F 2055 50 5 57B -

stress Montter- 2D F 2254 47EF 232C 23FE II1C ".

i ing Testa IF 57 F 38 5 12 5 40F 49 5 SEPE. 24PE GEP '

Ostensioning and s meterial T m .2DF 247C 2GF 242C 23FE 221C 4FE 222A 50W 2154 l TIlWON IRSSEN i Years After - '

Initial structural 20 5, 30 35. 40 Istagrity, Test . .

Type of Inspection M N Y N V N Y N V N V !

Type of Inspect $an .

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APPENDIX B l SUNNARY OF THE ' INSERVICE INSPECTION PROGRAM FOR !

POST TENSIONING TENDONS" l

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A. limpedioii Frequencies 1

Based on twin units, on-site inspection frequencies are established in :

compliance with Regulatory Guide 1.35, Rev. 3. After the fifth year of ;

inspection, a visual and grease inspection shall be performed on each unit for ;

every subsequent 5 year intervals. Every 10 years a physical (i.e., tendon lift 1 off, detensioning, and wire tensile test) testing shall be performed (See :

5 F;gure 1).

i B. Tendon Selection l

1. A total of 13 tendons shall be inspected through 5 years. If no abnormal !

degradation of the Post Tensioning System occurred, a total of 7 tendons are inspected thereafter, 3 vertical and 4 hoops. :

2. Tendons are randoniy selected from each group and are tabulated in Attachment 'A' to Appendix B.

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3. One tendon per group shall be designated as common tendon and should i' be kept unchanged after initial selection.

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4. If a randomly selected tendon from a group cannot be inspected due to ;

plant operating conditions, another sample from the group shall be '

selected. The tendon that was selected but not inspected should be .

inspected following plant shutdown and accepted on an indavidual basis.

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5. Except for the common tendon that has been inspected and found intact j during previous inspections, tendons should be excluded from the group r population during subsequent inspections. ,

6. If random sampling can not be assured a representative sample, between l pairs of buttresses or various height can be selected. Since inspection ,

can be performed while the unit is in operation, there may be certain i areas where inspection night result in high radiological exposure to !

personnel. Such tendons may be substituted with accessible tendons. !

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C. VisualInspection

1. The exterior surface of the containment should be visually examined to detect areas of large spall, severe scaling, Dcracking in an area of 25 square feet or more, other surface deterioration or disintegration, or grease leakage.

2. Tendon anchorage assembly hardware, such as bearing plates, stressing washers, shims, wedges, or buttonheads of the tendons selected shall be visually examined. For periods when only visual examination is performed on the containrnents, tendons should be visual;y examined to the extent practical without dismantling load bearing components of the anchorage or renuving grease caps.

3. Bottom grease caps of all vertical tendons should be visually exarnined to '

detect grease leakage or grease cap deformation. Removal of the grease cap is not necessary for this inspection.

4. Concrete surrounding visually inspected tendon anchorage should be checked visually to the extent practical for indication of abnormal material behavior.

D. Grease Sample Collec6on and Testing

1. Remove enough grease to allow for visual and laboratory analysis. l Visually examine the tendon casing filler, compare color and consistency with a sample of new tendon casing filler (Visconorust 2090P4 or equivalent) and check for any voids in excess of 5% of net duct volume or presence of free water within grease filler material.

2. The sample of sheathing filler grease irom each sample tendon shall be tested to the following National Standards (most current revision):

a. To determine water content, ASTM D95, " Standard Test Methods for Water in Petroleum Products and Bituminous Material by Distillation"

b. To detemine alkalinity, ASTM D974, " Standard Test Methods for Neutralization Number by Color Indicator Titration".

c. To detemine the concentration of water soluble chlorides, ASTM D512, " Standard Test Methods for Chloride lon in Water".

d. To detemine nitrides, ASTM D3867, " Standard Test Methods for Nitrite-Nitrate in Water".

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e. To detemine sulfides, APHA 428, " Standard Methods for Examination of Water and Waste".

3. The amount of sheathing filler grease removed and replaced should be compared to assess grease leakage within the strudure.

E. Tendon Uft Off to Check Tendon Force The tendon lift off force rmasured for each tendon should be compared with the linits predicted for the time of that test. The linits are as provided in Regulatory Guide 1.35.1. If the measured prestressing force of the selected tendon in a group lies above the predicted limit, the lift off force is considered to be an indication of the sample tendons acceptance. If the measured prestressing force of a selected tendon in a group lies between 95% of the predicted lower linit and 90% of the predicted lower linit, two additional tendons, one on each side of the first tendon, should be checked. If the prestressing force of both tendons is above 95%, all three tendons vill be considered acceptable.

F. Tendon Wire Sample and Test

1. A previously stressed tendon wire or strand from one tendon of each group shall be removed for testing and exanination over its entire length to detemine if any evidence of corrosion or other deterioration exists. A different tendon is selected for each successive inspection. The tendon selected may be the same as that selected for detensioning. All vires or strands identified as broken shall be removed for tensile testing and visual exanination.

2. Tensile tests are made on three samples from each cut ydre or strand, one at each end and one at mid length. The sample shall use the maximum length practical and the gauge length for the measurement of elongation shall be in accordance with the ASTM Specification A-421 (most current revision). The following information shall be obtained and recorded:

a. Yield strength ,

b. Ultimate tensile strength

c. Elongation at ultimate tensile strength G. Measurement of Grease Voids Check the grease samples for any voids in excess of 5% of net duct volume.

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1 H. Acceptance Cnteria !

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1. Tendon filler samples should show no change in physical appearance and meet the following rnanufacturer's requirements, as outlined in Regulatory ;

Guide 1.35, Rev. 3. (

i Chemical Prooerties l

Water Soluble Chlorides 10 ppm max !

Water Soluble Nitrites 10 ppm max !

Water Soluble Sulfides 10 ppm max Water Content 10% of dry weight max j;

2. The amount of grease replaced shall not exceed 5% of net duct volume when injected at original installation pressure. ,

3. Each tendon selected shall have an observed lift-off stress which exceeds 95% of the predicted lower limit. l

4. If the measured prestressing force of the selected tendon in a group lies ;

between 95% and 90% of the predicted lower unit, two additional tendons, ;

one on each side of the first tendon, should be checked for their ,

prestressing force. If the prestressing force of each of the second and i third tendon are above 95% of the predicted lower limit of the tendon, all .:

three tendons shall be restored to the required level of integrity and the tendon group shall be acceptable.

5. Tendon wires shall be frw of corrosion, cracks, other damagkand have l minimum tensile strength (240,000 psi) for three samples (oneTrom each end and one from the middle).

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6. No apparent changes have occurred in the visual appearance of the end {

anchorage or adja nt concrete surfaces since the last inspection. j

7. The voids are less than 5% of the net duct volume.

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8. De elongation observed during detensioning and retensioning, li corresponding to a specific load, does not differ more than 10% from that recorded during installation of the tendons. j 9; The average of all measured tendon forces for each group (corrected for !

average condition) shall be more than the minimum required prestress

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level at anchorage location. ;

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10. The measured prestress force for the sarne tendon selected in l subsequent surveillances shall not show loss larger than expected nor be -

less than the minimum required for the group. ;

i. The Content and Frequency of Repci&ig i

1. Wth more than one tendon with an observed lift-off force between the :

predicted lower limit and 90% of the predicted lower limit or with one _ l tendon below 90% of the predicted lower limit,' restore the tendon (s) to the required level of integrity within 15 days and perform an engineering evaluation of the containment on which test is being performed, and ;

provide a special report to the Commission within 30 days in accordance with Technical Specification 6.6.c, or be in at least Hot Standby within the i next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and Cold Shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .- 7 1

2. Wth any other abnonnal degradation of the structural integrity of the Primary Containment at a level below the acceptance criteria, restore the :

Containment on which test is being performed, to the required level of !

integrity within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , perform an engineering evaluation, provide a l special report to the Commission within 15 days in accordance with Technical Specification 6.6.c, or be at least Hot Standby within the next 6 ;

hours and in Cold Shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ;

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J. Remedial Actions

1. Additional testing and verifications shall be performed to justify the D, unacceptable condition and ensure the integrity of the Containment as' ,

stipulated in Regulatory Guide 1.35.1 and Regulatory Guide 1.35, Rev. 3 is maintained. :

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0 1 5 10 15 25 35 I I I I I I I Tirne after Initial Structural Integrity Testing of Containment, Years (Uft-off Testing Schedule, Containment No.1) 01 5 15 25 35 I I I I I i 1

Time after Initial Structural Integrity Testing of Containment, Years (Lift-off Testing Schedule, Containment tb. 2)

'l FIGURE 1. SCHEDULE OF UFT-OFF TESTING FOR TWO CONTAINNENTS AT A SITE kWaViresden\ tendons. wpm 6 w-- y #-.e- , , - . . .-- .-w r-- e,., ..m . - . . . , - - -. -m.-+ =.a.1,-> w+w-- + = - -

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APPENDIX B !

ATTACHNENT A !

i Terdon Surveillance -)

TENDON NUMBERS ,

Year After .i Initial Structural ;

integrity Test 1 3 5 10 15 l

Type of , H V H V H V H V H V inspection I

Visual 48AC 15C 48AC 15C 48AC 15C 48AC 15C 48AC 15C Inspedion of 56CB 15A 2CB 6C 3BA 28A 4BA- 30B 50CB 19A ,

End 12CB 20A 14AC 17A 12BA 23A 41CB 22A 53BA 13B ,

Anchorages 70B 47C 24BA 32C 21CB 5B 50AC 57AC Adjacent 2008 29A 37CB 42C 23BA 31C ;

Concrete 1CB 47CB 38CB Surfa and 12AC 57CB 49AC Prestress 56BA 608 68B Monitoring 21AC ~)

Tests >

l Detensioning 20CB 47C 2CB 42C 23BA 31C 4BA 22A 50CB 19A g and Material .

.. Tests t,

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1 TENDON NUMBERS Year After initial Structural Integrity Test 20 25 30 35 40 Type of ,

H V H V H V H V H V inspection Visua! Inspection 48AC 15C 48AC 15C 48AC 15C 48AC 15C 48AC 15C of End 39CB 25B 1BA 3B 4BCB 7B 49CB 25A 36CB 13A Anchorages 49EM 11A 47AC 12A 51AC 18A 51BA 188 48BA 27B Adjacent 71D 57BA 58BA 59D 69D Concrete Surface and Prestress ,

Monitoring Tes+s Detensioning and 49BA 11A 47AC 3B 48CB 18A 51BA 18B 36CB 13A Material Tests

. 'As applicable to a twin unit site LaSalle - Unit 1 1

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APPENDIX B U i

ATTACHNENT A !

Tendon SuneiRance l

i TENDON NUMBERS i

Year After l Initial Structural 1 integrity Test 1 3 5 10 15 Type of , H V H V H V H V H V Inspection i Visual 48EG 215C 48EG. 215C 48EG 215C 48EG 215C 48EG 215C ;

Inspection of 56GF 215A 2GF 206C 3FE 228A 4FE 2308 50GF 219A i Erd Anchorages 12GF 220A 14EG 217A 12FE 223A 41GF 222A 53FE 213B :

Adjacent 70F 247C 37GF 232C 21GF 205B 50EG 57EG !

Concrete 20GF 229A 47GF 242C 23FE 231C Surfa and 1GF 57GF 38GF -

Prestress 12EG 60F 49EG !

Monitoring Tests 56FE 24FE 68F l Detensioning 20GF 247C 2GF 242C 23FE 231C 4FE 222A 50GF 219A and Material ..

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TENDON NUMBERS Year After initial Structural 20 25 30 35 40 Integrity Test Type of H V H V H V H V H V inspection, Visual 48EG 215C 48EG 215C 48EG 215C 48EG 215C 48EG 215C Inspection of 39GF 225B 1FE 203B 48GF5 2078 49GF 225A 36GF 213A End 49FE 211A 47EG 212A 1EG 218A 51FE 218B 48FE 227B Anchorages 71J 57FE 58FE 59J 69)

Adja nt Concrete Surfa ard Prestress Monitoring Tests Detensioning 49FE 211A 47EG 203B 48GF 218A 51FE 218B 36GF 213A and Material Tests -

"As applicable to a twin unit site LaSalle - Unit 2 K\nla'dresdenitendons wpf20 I

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ML20056G366

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