ML20148P588

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Summary of 880316 Meeting W/Utils Re Containment Tendon Tech Specs for Facilities.Attendance List & Licensees Presentation Encl
ML20148P588
Person / Time
Site: Wolf Creek, Callaway, 05000000
Issue date: 04/01/1988
From: Dick G
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8804110316
Download: ML20148P588 (33)


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'8 WASHINGTON, D. C. 20$55 April 1, 1988 Docket Nos.: 50-482 50-483 LICENSEE:

Union Electric Company Wolf Creek Nuclear Operating Corporation FACILITY:

Cal 16way Nuclear Plant Wolf Creek Generating Station 1

SUBJECT:

SUWARY OF MEETING WITH UNION ELECTRIC COMPANY AND WOLF CREEK NUCLEAR OPERATING COMPANY TO DISCUSS CONTAINMENT TEND 05 'fECHNICAL SPECIFICATIONS FOR Tl;E CALLAWAY AND WOLF CREEK NUCLEAR GENERATING PLANTS The subject meeting was held on March 16, 1988. A list of attendees is included with Enclosure 1. is a copy of the licensees' presentation.

The licensees have submitted requests for changes to the technical specifi-cations. The staff, which has the proposed changes under review, had previously provided a prelininary assessment to the licen;ees, and requested the meeting."

The changes concerned the action statements associated with the various containrent tendon surveillances. Specifically, the licensees proposed having three levels of action statements depending upon the results of the particular surveillance. The proposed changes would also eliminate the requirement for less than 5% voids in the sheathing filler grease and replace it with a visual inspection of the containment exterior.

Further, it was proposed that the requirenentprohibftingmodechangeswhileinanactionstatement(Section3.0.4) would not be applicable for the containment surveillance, particularly in view of the fact that the actions involved providing a report to the staff.

With regard to the action statements, the licensees proposed the following:

1)

Surveillance - lift off force less than 90% of the predicted lower limit (Section 4.6.1,6.la)

Action"a" - restore the forces within 15 days or be in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within the following j

30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. (No change from current TS) 2)

Surveillance - visual inspection of detensioned tendon; determine tensile strength of wire samples; observe i

elongation upon retensioning; and assure observed i

liftoff forces exceed the average minimum design value (Section 4.6.1.6.c. & d).

l 8804110316 OB 402 i

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  • Action"b" - The results are considered to be indications of secondary significance. The action would entail providing a report to the staff within 30 days or be in hnt standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (Section 4.6.1.6.1 e).

3)

Surveillance - operability of sheathinp filler grease Action"c" - provide a report to the staff within 30 days and an engineering evaluation with 90 days or be in hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

The TS presently require restoration within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and a report within 15 days or be within hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for surveillance items 2 and ? above.

During the discussion, the staff indicated that it had no philosophical concerns with with the proposed changes in the action statements. However, a few of the proposed changes were not completely acceptable. After a caucus, the licensees proposed,the following changes to the proposed technical specification.

o Action statement "a" would apply to 4.6.1.6.1 d (observed liftoffstresses) o The TS would retain the requirement for less than 5% voids in sheathing fi'ler grease although it will be covered under Action "c" The staff proposed:

That it will consult with other staff roups regardin o

theproposaltoprohibitnodechangesfSection3.0.4)g while in the action statements o

That the licensee provide other examples where Section 3.0.4 is not applicable for specific action statements.

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It appears that the other changes as modified are acceptable.

The staff elso offered coments on the performance of surveillance procedures after reviewing previously submitted Special Reports on Tendon Surveillances.

The coments were:

1) licersee eng(ineering staff should use a checklist for visual inspections the contractors already use one) 4 i

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i 2) in order to more completely monitor the voids in the grease.

it was suggested that when sheaths'with high voids are refilled, some of the same tendons also be included in sub-i sequent surve111erces.

It will then give an indication of 4

whether the sheaths were ccepletely filled initially or the l

l; grease leaked out.

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George F. Dick, Jr., Project Manager Project Directorate - IV i

Division of Reactor Projects - III, i

IV, V and Special Projects

Enclosures:

As stated a

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DISTRIBUTION i

Docket File NRC A Local PDRs i

J. Partlow i

E. Jordan l

DCrutchfield GDick i

PDIY Reading ADR4/Co111ns l

JCalvo OGC-Bethesda JHall J

TAlexion i

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3-2) in order to more completely monitor the voids in the grease, it was suggested that when sheaths with hiqh voids are refilled, some of the same tendons also be included in sub-sequent surveillances.

It will chen give an indication of whether the theaths were cortpletely filled initia11y'or the i

1 grease leaked out.

! slV%il di Georgedr. Dick, Jr, Project Manager Project Directorate - IV j

Division of Rea: tor Projects - III, i

IV, Y and Special Projects Enclosures-I As stated 4

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Mr.' D, F. Schnell Callaway Plant Union Electric Company Unit No. 1 i

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Dr. J. O. Cereack Mr. Bart D. Withers CFA Inc President and Chief 4 Professional Dr., Suite 110 Executive Officer i

Gaithersburg, MD 20879 Volf Creek Nuclear Operating i

Corporation P. O. Box 411 i

Cerald Charnoff Esq, j

Thomas A. Paxter, Esq.

Burlington, Fansas 668fs i

Shaw, Pittman, Potts t Trowbridge t

i 2300 N Street, N. W.

Mr. Dan I. Bolef, President t

Vashington, D. C.

20037 Kay Drey, Representative t

Board of Directors Coalition Mr. T, P. Sharkey for the Eavironment j

Supervisor, Ccropl-iance St. Louis Pagior.

Union Electric Coropany 6267 Delmar Beulevard i

Post Office Box 620 University City, Missouri 63130 i

Fulton, Missouri 6G251 1

J U. S. Nuclear ReCulatory Comissien I

Fesident Inspectors Office

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RRf1 Steectr.an, Missouri 65077 Fr. Alan C. Passwater, Parager Licensing and Fuels l'nion Electric Company Post Offico Box 149 St. Louis, Missouri 63166 1

Manager - Electric Departr.ent Hissouri Public Service Comission

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301 W. High Post Office Box 360 l

Jefferson City, Missouri C510?

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Regional Administrator i

U. S. NRC, Reg (on III 799 P.oosevelt Road Glen Ellyn Illinois 60137 j

Mr. Ponald A. Kucera Deputy Director Departt:ent of Natural Resources l

P. O. Box 176 j

Jeffersen City, Missouri 65107 i

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Mr.' Bart D. Witners' Wolf Creek Generating Stetton Wolf Creek Nuclear Operating Corporation Unit No I j

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CC Jay Silberg, Esq.

Mr. Gerald Allen j

i Shaw, Pittnn, Potts & Trowbridge Public Heslth Physicist l

1800 M Street, NW Bureau of Air Quality 1 Radiation i

Vashington, D.C.

20036 Contro!

O! vision of Environtent i

i Chris R. Rogers, P.E.

Kansas Department of Health Manager. Electric Departnent and Environment i

Public Service Comission Forbes Field Building 321 i

P. O. Box 360 Topeka, Kansas 66620 9

Jefferson City, Missouri 65102 Mr. Gary Boyer, Plant Panager Regional Administrator, Region if f Wolf Creek Nuclear Operating Corp.

i U.S. Nuclear Regulatory Comission P. O. Box 411 4

799 Recsevelt Road Burlington, ransas 66839 Glen Ellyn, Illinois 60137 i

Regional Administrator. Region IV Senior Pesident inspector / Wolf Creek Ll.S. Nuclear Reguletory Comission c/o V. S. Nuclear Regulatory Comission Office of Executive Director P. O. Box 311 for Operations i

i Burlington, Kansas 66839 611 Ryan Plaza Drive, Suite 1000 j

Arlington, Texas 76011 l'

Mr. Robert Elliot, Chief Engineer Utilities Division Mr. Otto Maynard, Matager Licensing Kansas Ccrporation Comission Wolf Creek Nuclear Operating Corp.

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4th Floor - State Office Building P. O. Box 411 i

7epeka, Kansas 06612-1571 Burlington, Kansas 66839 l

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ENCLO5URE 1 i:

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MEETING _ ATTENDEES i

i Union Electric /WCNOC Centainment Tendon Meeting t

J NAME LFFIl1,JGM George Dick NRC - Pra i

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Randy Hall

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l Dave Shafer Union Electric-Lic.

t Scott liebel Union Electric-Engr.

Pramod K., Gupta WCNOC-Wolf Creek i

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Harold K. Cnernoff WCNOC-Licensing l

Maurice E. Dingler WCNOC-Engineering R. C, Slovic Bechtel-Engineering Steve Hoffman Bechtel-Licensing Eugene Thomas Bechtel-Engineering Guy Geddard Bechtel-Engineering f

l Gouten Beschi NRR/ESGB j

S. P. Chang NRR/ESGB C. P. Tan I;RP/ESGB Pans Ashar NRR/ESGB

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David C. Jeng NRR/ESGB 1

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ENCLOSURE 2 l *,,

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i SUBJEC1:

TECHNICAL EPECIFICATION SECTION 3/4.6.1.6 - CONTAINMENT VESSEL STRUCTURALINTEGRJTY(POSTTENS!0NINGSYSTFli$URVI!LLANCE).

l PRIMARY 151UE:

PLANT SHUTDOWN DUE TO A "POS$!!LE ABNORMAL DEGRADATION" BEFORE ADEOUATE

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EVALUATION EXCEPT FOR VERY MINOR ITDtS THERE IS h0 DISAGREEMENT ON THE SURVEILLANCE PROGRAM 04 ON THE $URVEILLANCE CRITERIA.

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6 PROPOSED AMENDMENT PHILOSOPHY Submittm1m ULNRC-1173 dated 8/18/85 KMLNRC-85-264 dated 12/6/85 Spec has been Restructured-3 Levolm of non-I compliance with appropriate action times 1)

Provides appropriate actions in the event containment structurmi integrity in quem-tionable.

2)

Providem prompt attention and corrective action to 1

ammure acceptable i

design margine are maintained if certain parameterm are degraded.

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Providem engineering evaluation for para-meterm which are indicatorm of future degradation, but not indica.tive of an inoperable contain-ment structure.

Removes thm requirement to verify gramme voids are less than 5%

but rather requires verification of no widespread gramme leakage.

Details of changes to be discummed later in the presentation.

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DESCRIPTION OF POST TEN $10NING SYSTEM A.

CONSISTS OF TENDONS, ANCHORAGES. DUCTS AND GREASE FILLER B.

USED IN C0hTA!NMENT STRUCTUAE C.

STRESSED. FAEASEO AND SEALED PRIOR TO PLANT OPERATION D.

COMPLETELY PAS $!VE SYSTEM e

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CROSS SECTION SEC TION A-A REACTOR BLCG

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DESIGN FEATURES OF PRESTRESSED CONTAINMENT A.

IMPOSES A CONSTANT INWARD LOAD ON CONTAINMENT SO THAT PRESSURE LOADS FROM LOCA EFFECTIVELY UNL0 ADS THE STRUCTURE.

B.

PASSIVE SYSTEM (NO ACTION IS REQUIRED FOR THE SYSTEM TO RESPOND TO Ah ACCIDENTCONDITION).

C.

DESIGN CONSIDERATIONS

' 1.

PEAX ACCIDENT PRESSURE IS LESS THAN 50 PSI.

2.

DESIGN PRESSURE IS 60 PSI.

3.

TESTED TO 69 PSI.

4.

PRESTRESS CREATES AN EFFECTIVE COUNTER PRESSURE OF 72 PSI.

5.

DESIGNLOADFACTORSASSUREELASTICBEHAVIOR(SMALLDEFLECTIONS)

TO 90 PSI.

6.

STUDIES ON OTHER SIMILAR CONTAINMENTS SUGGEST ULTIMATE CAPACITY IS IN EXCESS OF 120 PSI.

7.

TENDON STRESSES ARE GREATEST AT TIME OF STRESSING E

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INSERVICE INSPECTION & SURVEILLANCE RE0VIREMENTS TECH. SPECS.

SECTIONS 3/4.6.1.6 LIFT-OFF MEASUREMENTS WITHIN THE PREDICTED LIMITS

-- Failure requires restoration within 15 days and report to comission in 30 days or, Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> DETENSION TENDON FOR INSPECTION

  • Wires free of corrosion, cracks, damage

. No changes in grease Wire tensile strength min 240 ksi

-- Failure requires restoration within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and report to comission in 15 days or, Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> ELONGATION OF TENDON WITHIN 5%

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-- Failure requires restoration within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and report to comission in 15 days or, Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, a

Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 1

MIN. LIFT-0FF STRESSES ARE EXCEEDED

-- Failure requires restoration within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and report to comission in 30 days or, Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> I

VERIFY OPERABILITY OF SHEATHING FILLER GREASE BY ASSURING No voids in excess of 5%

a

. Min. grease coverage

. Physical propertiss are within tolerances for grease

-- Failure requires restoration within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and report to comission in 15 days or, Mode 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> NRC REG. GUIDES Reg. Guide 1.35 proposed Rev. 3 -

l Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments Comitted to compliance in Appendix 3A of the FSAR

SURVEILLANCE METHODS & DATA LIMITS Lift-off measurement Feeler gage method

. Verify tendon stress is > 90% of the lower tolerance band Grease sample testing

. One quart sample from each tendon end

. Visual exam to ensure grease coverage

. Laboratory testing of samples

- Water 10%

- Chlorides < 10 ppm

- Nitrates < 10 ppm

- Sulfides < 10 ppm

. Verify voids < S% during regreasing

- Vent through dome vent (vert.) or other end (hor.)

until 5 gallons of clean grease exits Wire sample testing

. One wire removed form each detensioned tendon 3-120 inch samples cut from wire; end-middle-end

. Each sample tested to ASTM A421 to verify > 240 ksi tensile ultimate; 100 inch samples Visual examination

. Archorage components - corrosion, excessive stress

  • Buttonheads - missing, broken, damaged l
  • Concrete - spalling, cracks, grease leakage

- exterior

- surrounding tendons s-

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8 ONE - YEAR PHYSICAL SURVEILLANCE CF THE CALLAWAY UNIT I CONTAINMENT BUILDING l

- TENDON LIFT 0FFS ACTV4L LITMF J P5_[.K)

TENDON f,IFTOFFS 5

EFFECTIVE JACK G7FRACE 90% LOWER LOWER UPPER FIPECYEO TFNDON END

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PRE 33VRE FORCf FrPCE LIMIT f.fMIT f.IMIT FORCE ACCEPTA0(t l

V-20 SMOP 169 3313 4313 1444.5 1411 1161 1286 1427 1361 YEt FIELD 169 8754 4140 13 Fi!

v-35 SHOP 169 8813 4136 1398.5 141f-1153 1270 1410 1352 YE3 e FIEF.D 169 8754 U20

1a V-65 SHOr 170 8754 4290 1424 1449.5 1193 1327 1469 1402 YES..

FIFLD 170 8813 4403.

1475 v-74 sitor 169 8754 4340 1445 1451 1152 127F 1402 1352 YEs

  • FIE1,D 129 8813 4)50 1457 i

1-Cs shSP 170 9364 66t.6 1382 1371 1110 1235 1369 1310 YES *

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cr1 ELD 170 G363 6480 1361 9-CB SHOP 169 9364 6423 1143 1324 1112 1236 1336 1311 TES FIE1.D 169 9363 6220_

1306 9-AC SHOP 170 9364 6457 1351 1339.5 1110 1235 1369 1310 YES FIFt3 170 9363 6320 131E 26-AC SHOP 170 9364 642')

1355 1339 1110 1235 1369 1310 YES

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FIELD 173 9363 6300 1323 5 *%

SHOP 170 9363 6600 1187 1357 1127 1252 1305 1318 YES FIELD 170 9'16 4 6346 1327 45-8A SMOP 168 9364 6140 12G6 1312.5 1146 1270 1402 1346 YE!

FtELD 168 9364 6410 1341 51-94 SHOP 170' 9364 6100 "276 1203.5. 1076 1193 1313 1.68 YES

, FIELD l'O 9364 t 6173 1291 I

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ONE - YEAR PHYSICAL SURVEILLANCE OF THE CALLAWAY UNIT I CONTAINMENT BUILDING

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COMPARISON WITH ORIGINAL INSTALLATION EFFECTIVE WIRES LIFTOFF FORCE (X)

TENDON END ORIGINAL

'6 1 YR 1URV ORIGINAL

'9 1 YR SURV LOSS PERCENTACE V-20 SHOP 169 169 1491 1411 80 5.4 FIELD 169 169 V-35 SHOP 169 169 1472 1418 54 3.7 FIELD 169 169 V-65 SHOP 170 170 1509 1449.5 59.5 3.9 FIELD 170 170 V-74 SHOP 170 169 1503 1451 52 3.4 FIELD 170 169 1-CB SHOP 170 170 1470 1371 99 6.7-FIELD' 170 170 9-CB SHOP 169 169 1474 1324 150 10.2 FIELD 169 169 9-AC SHOP 170 170 1491 1339.5 151.5 10.2 FIELD 170 170 26-AC SHOP 170 170 1491 1339 152 10.2 FIELD 170 170 5-BA SHOP 170 170 1482 1357 125 8.4 FIELD 170 170 45-BA SHOP 168 168 1479 1312.5 166.5 11.2 FIELD 168 168 51-BA SHOP 170 170 1388 1263.5 104.5 7.5 FIELD 170 170 Average Area at Installation 335.599 sq. in.

Constant X = -19.611 4

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SUMMARY

OF LIFT-OPF FORCES l

CALLAWAY UNIT 1 ALLOHABLE LIFT-OFF SURVEILLANCE TENDON END STRESS (KSI,)

LIFT-OFF NUMBER DESIGNATION MAXIMUM l MINIMUM STRESS (KSI )

Ava.

1 END A 165.0 148.6 174.57 > 16953

  • 1 END B 165.0 148.6 164.0 18 END A 175.0.

157.8 173.3

> 1 3.9 18 END B 175.0

.. 157.8 174.5 47 END A 173.3 156.7 168.9 '

47 END B 173.3 156.7 16 5. 9 ' > 167.4

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65 END A 175.0 158.0 175.54 173.27 65 END B 175.0 158.0 171.0 5

BUTTRESS A 161.1 145.0 154.0

> 153.15 5

BUTTRESS C 161.1 145.0 162.3 11 BUTTRESS B 170.0 153.0 156.0

> 158

  • 6 11 BUTTRESS C 170.0 153.0 161.2 14 BUTTRESS A 167.0 150.0 171.0

> 166' 5 14 BUTTRESS,B 167.0 150.0 162.0 18 BUTTRESS A 165.0 149.0 169.0

> 16 5

  • 6
  • 18 BUTTRESS B 165.0 149.0 162.1 35 BUTTRESS A 167.0 151.0 166.9

> 162.5 35 BUTTRESS B 167.0 151.0 158.0 45 BUTTRESS A 169.0 153.0 165.7

> 162.2 45 BUTTRESS B 169.0 153.0 158.7 47 BUTTRESS A 158.0 142.0 158.4

> 154.2 47 BUTTRESS B 158.0 142.0 150.0 '

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UNIT 1 TENDON SURUEILLANCE CALLAWAY THIRD YEAR LOSSES TENDON END INITIAL-ACTUAL AVERAGE PERCENT STRESS LITT-OFF LITT-OFF CHANGE -

KSI STRESS STRESS AVERAGE KSI KSI HORIZONTAL TENDONS 5-A 154.0 5

C 176.35 162.3 158.2 10.29 11 B

156.0 11 C

184.60 161.2 158.6 14.08 14 A

171.0 14 B

177.04 162.0 166.5 6.26 18 A

169.0 18 B

177.20 162.1 165.5 6.60 35 A

174.0 l

35 B

179.78 166.5

  • 170.3 5.27 45 A

165.7 45 B

180.59 158.7 162.2 10.18

)

47 A

158.4 47 B

170.24 150.0 154.2 9.42 AVERAGE HORIZONTAL LOSS =

0.910

  • 169 WIRES i

UNIT 1 TENDON SURVEILLANCE J

CALLAWAY THIRD YEAR LOSSES l

TENDON SND INITIAL' ACTUAL AVERAGE PERCENT STRESS LIFT-OFF LITT-OFF CHANGE KSI STRESS STRESS AVERAGE KSI KSI i

l 1

VERTICAL TENDONS 1

A 173.6 1

B 178.31 173.0

,,173.3 2.80 18 A

173.3 18 B

185.92 174.5 174.0 6.41 47

'A 168.9 47 B

183.72 165.9 167.4 8.88 l

65 A

171.0 65 B

185.92 175.54 173.3 6.78 4,

AVERAGE VERTICAL LOSS =

0.937

  • 169 WIRES i

i II i

4 9

a

FIRST - YEAR PNYSICAL SURVEILLANCE OF THE WOLF CREEK UNIT I CONTAINMENT BUILDING TABLE VIII.a:

SUMMARY

OF DATA SMEET 9.0

- TENDON LIFT 0FFS (Revised As For BCR F-009) j 1

3TJA: 1.!MCFP FPSI.2) l TtIDCE LTTMTN EFTgg;;yg Jagg ATTRAGE gCL Lcist Lp41 VFFER EEPEC"ED ttrDos tyB vtus 50.

FEESSUtt FORCE 701CE LTNTT tw LTMN PCRC1 Ac-* PM a' s l

T-20 suor 170 88u 4M7 1454 1400 u27 1252 1.3 M D33 ft3*

y ;t:.3 170 8754 4020 134S Y-13 5500P 170 Stu 4043 U32 1333 1993 1213 1360 U02 TE3 '

FIELD 170 5754 3963 1326 Y=s3 i SHOP 170 4734 412 >

leu 1632 lus 1243 13H U27 TE3' i

l TIE:.D 170 88u 4340 1452 V-ko SMOP 170 4734 4183 1400 3404 M43 l U68 1410 U32 133 FTE:.3 170 8813 4207 1407 l

1-c3

  • EP l

170**

1362 'l 6937 1474 1422 1047 1203 134.4 1278 I

TES

  • i FTF D I 170**

9363 il 6470 1370 I

9-C8 SHOP 170 9362 6943 1471 pg7 1968 1185 1327 1268 l

TE**

l rte:.D 170 1345 6130 1302 i

e 9-ec JMCP l 170 l 9366 6330 l

1382 USO i

1068 1155 1 1318 1260 l

T13' TTP D 1 170 I 9365 4297 1333 I

I i

26-4/:

l FTT!.3 l 169 l 9366 3x0p 4347 1386 0 1339 1987 12 3 1332 12H l

l TE**

1 169 I 9365 6290 1332 l 3-na l 3MCP 16 9"' l 1362 l 6337 1342 1331 ugs ugg uf7 1333 l

Ygy*

l Titi.D 169*" I 9366 I 6710 1421 05-84 SMOP i 170 9362 66.10 i

1407 1409 1083 1202 1332 1283 l

TE3' l rte:.3 I 170 93 6 667e i lau 1

38-84 i SwCP l 170 1 9362 i 6237 i u23 uas 101s I n32 u13 i :.227 i

rES=

l FTE:.3 l 170 1 9366 I 6400 1 1372 i

i I

  • Tendons Force uesaded Upper Limit.

Section 2, Part Y for a detailed discussiim.

    • Installation Recor:Is show 169 effective wires in tendon.
      • Installatica Recotts show 168 effective wirts in tendon.

.,,-,,,,,-.,_,..,,.--.,,,,,m,yv,r.

I

(

r2 mar - van rwr:1ca, savssu. ace or xxx WOLF CREEK UNIT I COWEA31GREt EUILDIN3 i

l TABLE III.a:

COWARISON WITN ORIGIEAL IESTALLATION CBevised as per BCE F-009)

E77ECT7VE MERS LIFM FP FORCE (K)

TENDON ORIGINAL 811RemV ORIGINAL ** 6 1 YB avn, LOSS PERC r.u RAGE Y-20 170 178 1493 1400 93 6.2 V-35 170 170 l

1487 1339 148 10.0 V-GS 170 170 1500 1432 64.

4.5 Y-74 170 169 1545 1404 141 9.1 169 170 1480 1422 58 3.9 1-CB***J' 170 170 1492 1387 105 7.0 9-C3 9-AC

'170 170 1489 1358 131

8. 8,

26-AC 169 168 1518 1359 159 102_4 5-8&***

163 169 1511 1381 130 8.6 45-34 170 170 1454 1409 49 1.4 31-aA8 170 170 14M 1348 36 4.0 Wire tendon with Bet Fortas equal to 162 wire tendas.

Based upon the Stress Yalues given in specification CAA997204, Rev. 1 and 6

  • e number of effective wires.

streesing Becord indicates one less wire at. original installation than found during surveillance. Saa section 2,. Article III.

s 3075 For Tendus Y20, V63, V74, 26AC and 313A double button headed and split wirse noted at er4sia=1 installation were seasideM affee.tive since they are still re+=t=4== the required force at the tino of surveillanen sad are meeting the requirements of ASTN A421.

I I

e u -. t.

Sut#4ARY OF LIFT-OFF FORCES TABLE 1 PRELIMINAR/

Wolf Creek Generating Station, Unit 1

(

Tendon End Allowable Lift-off Surveillance Lift-off Number Designation Force (kips)

Force (kips)

Maximum Hininum

$V1 End A 1397 1272 1406

  • V1 End 8 1397 1272 1365 V18 End A 1411 1285 1483 V18 End 8 1411 1285 1391 V47 End A 1408 1282 1383 V47 End 8 1408 1282 1495 V65

, End A 1421 1293 1403 V65 3nd 8 1421 1293 1495 HSAC Suttress A 1383 1254 1399 HSAC Buttress 8 1383 1254 1392 H11CB Buttress 8 1397 1267 1386 H1108 Buttress C 1397 1267 1392 i

l H148A Buttress A 1369 -

1243 1387 1

H148A Buttress 8 1369 1243 1399 l

H188A Buttress A 1394 1265 1416 H188A Buttress B 1394 1265 1425 H358A Buttress A 1397 1268 1432 H358A Buttress 8 1397 1268 1425 H458A Suttress A 1390 1261 1435 H458A Buttress 8 1390 1261 1385 H478A Buttress A 1322 1199 1252 H478A Buttress 8 1322 1199 1359

  • 169 wfres See WCR Nuders: WC-1, 3,4,5,6,7,8,9,10,13,14,15,16 w

e

-,e ww---

w


e<

, ~. _ - -

--r-.--- - - - - - -,,,

wn-.

TENDON SURVEILLAMCE Table 5 PREUMINARY Wolf Creek Generating Station, Unit 1 Tendon End l Initial Actual Average Percent Percent Number Butts' Force lift-Off Lift-Off Change of Initial Force Force Average Average L

H5 A

1449.10 1398.52 1393.14 3.73 0.%2 C

1391.76 r

H11 B

1453.80 1388.20 1385.50 4.70 0.953 C

1382.76 H14 A

1441.20 1336.50 1392.9.0 3.35 0.966 8

1399.24 H18 A

1440.50 1415.80 1420.50 1.39 0.986 8

1425.27 H35

'A 1433.CO 1431.50 1408.20 1.77 0.982 8

1384.88 H45 A

1414.90 1434.52 1429.90 1.06 1.01 0 B

1425.27 H47 A

1351.00 1251.50 1305.20 3.42 0.965 8

1358.85 VI A

1486.77 1405.97 1385.40 7.44 0.925 8

1364.80-V13 A

1483.87 1482.94 1436.97 3.16 0.968 8

1391.00 V47 A

1476.23 1383.00 1438.90 2.53 0.975 8

1494.82 V65 A

1501.07 1403.00 1417.60 5.56 0.944 B

1432.27 Avera9e Horizontal Loss = 0.975 Average Vertical Loss = 0.953 j

W

JUSTIFICATION FOR SNUPPS PROPOSAL A.

NONE OF THE "POSSIBLE ABNORMAL DEGRADATIONS" ADDRESSED BY SURVEILLANCE PROGRAM WILL REST'LT IN IMMEDIATE DANGER CONTAINMENT INTEGRITY. RATHER. IT PROVIDES AN EARLY WARNING OF CONDITIONS WHICH M4Y REQUIRE TIMELY ATTENTION.

1.

SYSTEM IS PASSIVE AND SEALED CHANGESINSYSTEM(ISLOADLOSSAND/ORCORROSION)ARE BOTH CONTROLLED AND EXTREMELY SLOW.

TIri!NG OF SURVEILLANCES SUFFICIENT TO PROVIDE EARLY WARNING OF OEGRADATION LONG BEFORE IT BECOMES A SAFETY HAZARD.

1 PRESERVATION OF SYSTEM CONFIRMED BY HISTORICAL PERFORMANCE.

\\

i v

A-

O

~

2.

SUBSTANTIAL SAFETY MARGINS EXIST IN DESIGN EVEN IF LOSSES ARE GREATER THAN EXPECTED (INDICATES NO IMMEDIATE DANGER EXISTS).

PRESTRESSING AT END OF 40 YEARS CREATES AN EFFECTIVE COUNTER PRESSURE APPROXIMATELY 1.5 TIMES MAXIMUM ACCIDENT PRESSURE.

EVENGREATERAMOUNTSOFPRESTRESSINGEXISTDURING5ARLIER LIFE OF PLANT (LOWER LIMIT MAY SUBSTANTIALLY EXCEED REQUIRED PRESTRESSING LEVEL).

  • ULTIMATE CAPt. CITY OF CONTAINMENT IN EXCESS OF TWICE THE DESIGN PRESSURE.

CONTAINMENT PERFORMANCE ESTABLISHED BY A PRESSURE TEST.

e

l i

12 3.

IONIT0 TING OF FRESTRISS 2

l m.ite,ias as arestrees ieveis i. s e.stsi..st o.as u s.a.. a.

f primary sosteo of internation from which the coatsissest is evalsang East tenden la the saapie is subjected to a lif t-of f test using a es11-

)

brated jack to deternise the tension. Tesdos elossatica mesessements

=j are siso taksa to provide verifienties that so gross errors are made is j

the tension measurenests and to verify toados late 8sity.

The satsal seattering of the prestress level is sosposed of several parts:

(1) a definition of lif t-of f s (1) the interpretation of the rossits s d. sosse-l gsently, the asseptability of the rossits; (3) sensurements of elongs-2 ties; (4) de tensiesing; and ($) rotonatosias. Only the definities of lif t-off sad the itterpretation and scoeptability of the rossits will be s

considered la this eksyter. Rotensioning sad elossation are considered La Chap. S.

Excerpt from Nuggg_cg_,7I9.

h

?

l i

~

\\

a PROPOSED AMENDMENT l

Action m

1 Remaine unchanged manures present i

containment integrity, or shutdown Action b

Rep 1 meed by proposed Actions b,

c, d

o Propormd Action b

non conforming parameter that deem not degrade integrity.

f Appliam to wire gramme condition, retensioning and lift off stremmee Provides for 30-day Engineering Evaluation, and 30-day Report to

NRC, or shutdown

y i

Proposed Action c

non conforming parameter which may allow future degradation Appliam to leaking

gramme, gramme coverage or chemical propertime end anchorages and containment surfaces Provides for 90-day Engineering Evaluation, and 30-day Report to NRC Proposed Action d

Reducem the impact on plant operation consistent with the allowable times in Action a,

b and c.

l Surveillance e.1 deletes requirement to verify gramme void Providen visum1 exam to i

ammure no widespread gramme leakage

.. -