L-76-200, Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons

From kanterella
Revision as of 15:32, 5 January 2025 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Letter Request to Amend Appendix a of Facility Operating Licenses DPR-31 & DPR-41. Proposes Technical Specification Changes Relating to Surveillance of Containment Building Tendons
ML18227D855
Person / Time
Site: Turkey Point  
Issue date: 05/20/1976
From: Robert E. Uhrig
Florida Power & Light Co
To: Stello V
Office of Nuclear Reactor Regulation
References
L-76-200
Download: ML18227D855 (11)


Text

NIRC FORM 195 I2. TE)

V.S. NUCLEAR AFGULATORYCO!iIMISSION DOCILET N ViM 50-2 / 51 NRC DIETRIEU PION vo PART EO DOCKET MATCRIAL FILL'UMBER MR, VXCTOR STELLO>> JR, I=ROiM:

FLORXDA POWER & LIGHT COMPANY MIAMI, FLORIDA MRo ROBERT Eo UHRIG DATE OI'OCUMENT 5/20/76 DATE RECEIVFO 5/26/76

$4LETTCR gOA IGINAL OCOPY DESCRIPTION POTOAIEED P~VNC I.ASSI F I E D PROP INPUT FORM FNCLOSURF NUMBER OF COPIES RECEIVED THREE SIGNED LTR, NOTORXZED 5/20/76 W/ATTACHED,~ ~ ~, ~ ~ ~

FURNXSHXNG XNFORMATXON CONCERNXNG LISENSE

!IU"IDT, REQUEST TO CHANGE TECH SPEC TO AMEND APPENDIX A OF FACXLITY OPERATXNG LXCENSES DPR-31 AND DPR-41

'LANT NAME.

TURKEY POXNT 3 & 4 XCKN07KZPGEB DO NOT REMOVE ASSIGI.':""D AD:

)'BAliCH CHT?F:

Pi<OiMT I:A!:!1(i.""i'.

LIC, ASST.:

PARRXSH FOR ACTION/IIMI=ORi)ATION

~526/76 RJL ASSI GI -D AD:

LXC. ASST.:

BEG FXL.".

I,

'DB I k.IO OHi D lid.I:I:" O'ETLlE SYSTEM!S SAir iY SCHHO" TCR

.;.~!lAHOYA IfsTE RidAL DISTRII)UTIO8'iT ttTPO

<~ItjII>>

AT,1~I!'Q

),~ ~T~>>)7 GOSSICK F. STA~i WIPC CASK HANAUr.R QP.BL" SS

~Q~&~lC 'SNAGÃFPHT IQYY P COLLIIIS HOU8'TON PETERSON hELTZ IILPLTT"~S SKOVHOLT W LPDB: MXAMI FLORIDA

'PTP

'SIC

.",CITS/~~~~a Ii NRC FORM 195 {2.76) 2!lGT'r"BII'G KIITOHTi

~i?D5 PAE'ILTCII HIL~CTOH K4. ETY ROSS NOVAK ROSZTOCZY CHECK SAL'I/KKN HUTZr"HG EXTERNAL DISTRIBUTION I A~lFL~XL13 REG. V-Ir.

COIISIJI(TANTS XPPOLI iO OPI",RA TN,": RDC'XORS STiZ LO OPi RATiÃG TiY'H EIS I".ndi SHAO LAKH SCHh>> IIC "H GRXIIES SITT: SAF~~Y 4 E'IVIHO AILALYSXS DIZGOII k hHJLL "H

'"ROOD".V"~l IIATL LAD ULHIHSO!'KIL S:

C." ".!,"LL S 'ZDP HUa: Ahl SIT-AIIAL S S

VOLL!""H 2'".ICH J.

COLLT'IS ILH"GZB it I

COIIITROLHUMBE'I

f

'I H

t A

9 f'1V gg t+t

~

l k

I, J'g Director of Nuclear Reactor Regulation Attn:

Mr. Victor Stello, Jr., Director Division of Operating Reactors U.

S. Nuclear Regulatory Commission Washington, D.

C.

20555

Dear Mr. Stello:

Re:

Turkey Point Units 3 and 4

Docket Nos.

50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 FLORIDAPOWER 5 LIGHT COMPANY May 20, 1976 L-76-200

,'<4, l,j,(;,,

fitEil~JQf

~~ iI ~pe) ]Qg ~ $9) t Ue>2~I. 0 "2C 3L1/g~

ZJ w/

N' J li,,,i, I

In accordance with 10 CFR 50.30, Florida Power

& Light. Company submits herewith three (3) signed originals and forty (40) conformed copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41.

This submittal proposes Technical Specification changes relating to the surveillance of containment building tendons at. Turkey Point Units 3 and 4.

The proposed changes are as described below and as shown on the accompanying Technical Specification pages bearing the date of this letter in the lower right hand corner.

Pa es 4.4-4 and 4.4-5 Technical Specification 4.4.6 is revised to require extensive tendon surveillance for Unit 3 only, with a more simple visual inspection required for Unit 4.

The proposed surveillance program would eliminate costly duplication of effort without sacrificing any potential for discovering unsatisfactory tendon performance.

A safety evaluation of the proposed surveillance program is attached.

The proposed amendment has been reviewed within Florida Power 6

Light Company and the conclusion reached that it does not in-volve a significant hazards consideration, therefore, prenoticing pursuant to 10 CFR 2.105 should not be required.

Yogis very truly, I

~ 'Ig/J r

Robert E. Uhrig Vice President REU/cpc I

ghee

'f'L.

P'ttachment cc:

Norman C. Mosely Jack R.

Newman, Esq.

PEOPLE... SERVING PEOPLE

4.4.6 TENDON RVEILLANCE 4.4.6.1 'est Fre uenc Containment tendon inspections, as described below, will take place at the end of the fifth year and every fifth year there-after from the date of the structural integrity test for Unit 3 (July 4, 1971) and for Unit 4 (February 19, 1972).

Tendon sur-veillance may be conducted during reactor operation.

4.4.6.2 Unit 3 a): Visual Inspection All 'tendon anchorage assembly hardware such as bearing plates, stressing

washers, shims, and buttonheads shall be visually inspected-.

b)

Lift-offReadings Take lift-offreadings on each tendon in the selected sample to monitor loss of prestress.

Sample selection is specified in Section 4.4.6.4.

c)

Wire Inspection One horizontal, one vertical and one dome tendon will be relaxed and one wire will be removed from each as a sample.

(At subsequent inspections, different tendons will be used for the dome and hoop samples).

Wires will be visually inspected for corrosion and pitting.

Tensile tests will be performed on three (3) samples cut from each wire (one from each end and one from the middle) of a length equal to the maximum length acceptable for the test apparatus to be used.

After samples are taken, tendons will be retensioned.

and final lift-offreadings will be taken.'.4.6.3 Unit 4 The Unit 4 containment has the same design as the Unit 3 contain-ment.

Both containments are located at the same site and were constructed in the same way by the same contractor during a.period of continuous construction.

Therefore, Unit 4 requires only the following inspection.

The tendons in the selected sample shall be visually examined to the extent practical without dismantling load bearing components of the anchorage.

4.4.6.4 Sam le Se'lection a)

For the initial fifth year inspection, the following tendons will be selected.

Six dome tendons distributed to provide representative sampling, i.e.,

two from each 60'roup (three families of tendons).

4. 4-4 5/20/7 6

2)

Three vertical tendons distributed to provide repre-sentative sampling.

3)

Ten hoop tendons randomly distributed to provide representative sampling.

b) If the initial fifth year inspection shows that there is no abnormal degradation of the prestressed tendons, 'the sample for subsequent inspections may be selected as follows:

1)

Three dome tendons distributed to provide representative sampling, i.e

, one from each 60'roup.

2)

,Three vdrtical tendons distributed to provide representative sampling.

c)

.3)

.Three hoop tendons randomly distributed to provide representative sampling.

The results of any fifth year inspection which shows abnormal degradation of prestressed tendons will be evaluated to determine appropriate followup action.

4. 4-5 5/20/76

0

SAFETY EVALUATION INTRODUCTION 10 CFR 50, Appendix A, General Design Criterion 53 entitled "Provisions for Containment Testing and Inspection" requires, in part, that reactor containments be designed to permit (1) periodic inspection of all important areas and (2) an appropriate surveillance program.

The inservice inspection program for containment tendon surveillance, at Turkey Point Units 3 and 4 is specified in Section 4.4.6 of Appendix A to Facility Operating Licenses DPR-31 and DPR-41.

This Safety Evaluation supports a proposed amendment which requests that Technical Specification 4.4.6 be revised such that:

a)

Based on the satisfactory results which have been obtained for inspections conducted to date, the Unit 4-containment tendons receive only a visual inspection.

b)

. The initial fifth year inspection on the, Unit 3 con-tainment fully inspects 3 additional dome tendons and 7

additional hoop tendons.

c)

Based on a satisfactory Unit 3 fifth year surveillance, the sample size may be decreas'ed to include only 3 dome

tendons, 3 vertical tendons, and 3 hoop tendons..

Differen't dome and hoop tendons will be chosen for each inspection and will'e randomly distributed to provide a representative sample.

DISCUSSION The containment design of Turkey Point Units 3 and 4 provides for a pre-stressed concrete structure with ungrouted tendons.

Surveillance tendons are chosen such that a sample is obtained from each major tendon type (dome, vertical and hoop).

The s'pecific choices within each type are selected to provide tendons which are subject to various environmental exposures.

The proposed amendment will result in expanded surveillance of Unit 3 containment tendons for the initial fifth year inspection.

The proposed amendment. will also result in the examination of different dome and hoop tendons at each inspection rather than examination of the same tendons.

In changing the tendons, a

representative sample will be maintained.

One tendon from each of the three dome groups will be included in each inspection.

The hoop tendon sample will still be selected to endeavor to cover a full 360'f the containment.

The vertical tendon

sample, which will remain unchanged, will still provide a

V sampling from three different sectors of the containment.

Therefore, the inspections will continue to properly provide sampling that is representative of sections of the containment with potentially different environmental exposure.

In fact, the sampling will be improved by selecting different dome and hoop tendons for each inspection because a larger number of different tendon locations will be inspected over the life of the plant.

The elimination of lift-offtesting and wire removal from the Unit 4 tendon surveillance specification is justified because the Unit 4 containment has the same design as the Unit 3 containment.

Both containments were built by the same contractor during a continuous construction period.

They are located less than 1000 feet apart and experience the same environmental exposures.

The phenomenon of greatest concern which we are trying to monitor is corrosion of the tendon wires.

Because of the similarities des-cribed above, there is no basis for expecting one containment to experience more or less corrosion attack than the other containment.

Other phenomena such as stress relaxation, temperature variation of the wire, concrete deformation, and differential thermal expansion between the concrete and the tendon can lead to loss of tendon prestress and must also be considered.

However, because both containments have the same external environment, the same engineering design, and experience the same internal operating conditions, these phenomena can be expected to have the same probability of occurrence in either containment.

Therefore, extensive surveillance of one containment will provide an adequate sampling of tendons to ensure that't'.he tendons of both containments-are not experiencing deleterious effects caused by these phenomena.

CONCLUSIONS It is concluded that containment structural integrity will not be degraded by using the proposed surveillance program and. that the surveillance program meets the intent of General Design Criteria 53 as well as the intent of the current Technical Specifications.

Based on these considerations, (l) the proposed change does not increase the probability or consequences of accidents or mal-functions of equipment important to safety and does not reduce the margin of safety as defined in the basis for any technical specification, therefore, the change does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not. be endangered by operation in the proposed

manner, and (3) such activities will be conducted'n compliance with the Commission's regulations and the issuance of this amendment will'ot be inimical to the common defense and security or to the health and safety of the public.

4

/

'7

sm,m a~ vxonzoa

)

)

SS COUPZX Op 'MM

)

Robust E. Ohmic, bain'2roh 6ely m>em, @apices anC aaya."

Than ho 9.cI a V9ca 'PdaaManh eG PXeri@a Pomade 6 X9ghC, Company<

@ha Xiconcae harahng

'Shah ha haa mcaceCa6 She foregoing 6emzaank,"

Chat Cha ahahczcnha rm6a in theo

@AM 6ocmnant. era Irma an@ corzcch Ce

@ha baal oC hie: keeuicdga, inGozmaCkea and balkaGI, m6 @hat, ha. ia auhhezA-c8 Co a::ccI0ICa Who Gocuzmnt; en babas eS'aM Lkcancaa Eo azCK',. 0 rg SuLIcIcr9bc6 an6 axeman Ce bcIfora ma WI.D ~4 ~

Bay a2 t

3,976, Notary c,

n an Re~ 4 a Cme y eR e~ ~~ +~~~

~~

p08 C S ATE of OR 0 A7 IAR(p QY COMMISSION EXPIRES NPV, 90 I 97'O~WW~

QNERAI. INS( umRWRgRS, kty comn9.aoion a>~i<zaI

~

~

(~ '

E J

p f

1 H

,I p

If p

t

~

(

I I

J I p r

f Il I

tr

,')IHH J'

'I I

H I .)

'I p Ir

)

, ~

r pf r

H

)).

r,

(

I,Q pf 'I