ML19210A817

Tech Spec Change Request 11 Supporting Licensee Request to Change DPR-50,App A,Re Tendon Surveillance Program Requirements.Certificate of Svc Encl

ML19210A817
Person / Time
Site:	Three Mile Island
Issue date:	05/14/1975
From:	Arnold R METROPOLITAN EDISON CO.
To:
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ML19210A816	List: ML19210A815 ML19210A817
References
NUDOCS 7910310709
Download: ML19210A817 (13)

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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 11 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. FrR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

METROPOLITAN EDISON COMPANY i

By VicV Presidint

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Sworn and subscribed to me this 14th day of May , 1975 d+~ 72 c-Notary Public

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATIER OF DOCKET No. 50-289 LICENSE NO. DPR-50 METROPOL.2AN EDISON COMPANY

'Ihis is to certify that a copy of Technical Specification Ch'ange Request No.11 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, dated May 14, 1975, and filed with the U.S. Nuclear Regulatory Commission on May 14, 1975, has this 14th day of May been served on the chief executives of Londonderry Township, Dauphin County, -

Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:

Mr. Welcon B. Arehart, Chairman Mr. Charles P. Hoy, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R.D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 P.O. Box 1295 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COMPANY By l _

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e Metropolitan Edison Company Three Mile Island Nuclear Station Unit 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request 11 Licensee requests revision to Appendix A of the Technical Specifications for its Three Mile Island Nuclear Station Unit 1 (TMI-1) . As a part of this request, revised pages for Appendix A, marked " Change Request 11",

are attached.

Change Request 11A Alter the requirements of the Tendon Surveillance program related sections of the THI-1 Technical Specifications , Appendix A, by removing the current section 4.4.2.1 (pages 4-35 through 4-36b) and replacing them with the revised section 4.4.2.1 (pages 4-35 through 4-36b) .

Reason for Change 11A The change is necessary to ensure that the Tendon Surveillance program can be conducted. Further, the change, if implemented, would serve to make the THI-1 Technical Spe'cifications consistent with Regulatory Guide 1.35 (Rev.1) and thereby more accurately describe the required tendon surveillance program.

Safety Analysis Justifying Change 11A Although the change involves a change to a safety-related test described in the TMI-1 Technical Specifications , it does not involve an unreviewed safety question in that if implemented:

. . a. it will not increase the probability of occurrence or consequences of an accident as analyzed in the TMI-1 Final Safety Analysis repo rt (FSAR),

b. it will not increase the probability of an accident not described in the TNI FSAR, and

c. it will not reduce the margin of safety defined as the basis for any Technical Specification.

Further, it should be noted that the proposed change, if implemented, vould allow for a more accurate assessment to be made of the time behavior of tendon relaxation and concrete shrinkage.

Change Request 11B Page 4-36d. In section 4.4.2.2.B .2, the third line , change "+ 0.004 In the fifth line of 4.4.2.2.B.2, and in the in/in" to "+ 0.0004 in/in". ,

third line of 4.4.2.2.C.2, change " Engineer" to " Station / Unit Superintendent."

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Reason for Change 11B The proposed changes correct a typographical error and remove any ambiguity as to whom deficiencies should be reported.

Safety Analysis Justifying Change 11B There are no unreviewed safety questions in that the changc, if implemented, would simply serve to make typographical and editorial corrections.

Change _ Request llc Page 6-13. In the first line of 6.7.3.C.4, change "6 months" to "three months".

Reason for Chance Recuest 11C The change is proposed to make Technical Specifications 6.7.3 and 4.4.23 (renumbered as 4.4.2.1.4) consistent and in accordance with the reporting requirements of Regulatory Guide 1.35 (Revision 1) .

Safety Analysis Justifying Change llc -

There are no unreviewed. safety questions in that the change si= ply provides for consistency and requires reporting in accordance with the more stringent reporting requirement.

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Change Request No. 11 4.4.2 Structural Integrity Applicabili(g Applies to the structural integrity of the reactor building.

Objective To define the inservice tendon surveillance and the ring girder inspection programs for the reactor building prestressing system.

Specification 4.4.2.1 Inservice Tendon Surveillance Program The surveillance program for structural integrity and corrosion protection conforms to the recommendations of the U.S. Atomic Energy Commission Regulatory Guide 1.35, Revision 1, " Inservice Surveillance of Ungrouted Tendons in Prestressed l Concrete Containment Structures." The detailed surveillance program for the prestressing system tendons shall be based on periodic inspection and mechanical tests to be performed on selected tendons, as specified hereaf ter.

4.4.2.1.1 Frequency -

The frequency of the inspection and testing shall be as follows:

1st Inspection Period - one year af ter 'The Structural Integrity Test "

2nd Inspection Period - three years af ter 'The Structural Integrity Test "

3rd Inspection Period - five years after "The Structural Integrity Test "

4th-10th Inspection Periods - Every five years thereaf ter throughout the life of the unit.

l 4-35 ge q }r7 s/

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L..ange Request No.11 h.h.2.1.2 Selected Tendons Representative samples f rom homogeneous subgroups of tendons have been sclected for periodic inspection. Table 4.4-1 shows the selected tendons and their corresponding inspection periods.

4.4.2.1 3 Tests l The t.ests to be performed at each periodic inspection on the selected tendons shall consist of the following:

a. Tendon Prestress Force Confirmation Test

1. Lif t-off test shall be performed on all selected tendons, with the maxi-mum force greater than the maximum inservice prestress force. The lift-off force and the corresponding elongation shall. be recorded. Af ter the lif t-off the tendon shall be subjected to an unloading cycle going down to complete detensioning, and inspected for broken wires. Af ter inspection, the tendon shall be retensioned to the lif t-off force level observed during detensioning. Any changes in the shim thickness shall be recorded.

2. The acceptance criteria fer the allowable jacking load and allowable l tolerances during the lif t-off test shall be established prior to performing the test. The measured prestress force shall be checked against the predicted lower bound and upper bound at the time of test. The criteria taken into account shall include the following items:

a. The time that has elapsed since the tendon was stressed

b. The location of the tendon in the structure

c. The tendon configuration straight or curved

d. The approximate age of concrete at the time the tendon was stress ed 3 rs Fg Isv

e. The initial lift-off force of the tendon  ;

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Change Request No.11

f. The lift-off force from the previous lif t-off test (if used for i more than one lif t-off test)

g. Stress relaxation in the wire

h. Temperature variation in the wire

i. Shrinkage, creep, and temperature stresses in the concrete J. Tolerances for possible errors in jack pressure, gage readings, and elongation measurements.

3. The allowable limit shall be one defective tendon out of the total l sample population. If one sample tendon is defective, an adjacent tendon on each side of the defective tendon shall also be checked. If both of these tendons meet the acceptance criteria, then the single deficiency is considered unique and acceptable,

b. Tendon Physical Condition Test

1. Table 4.4-2 shows the tendons and their corresponding inspection periods, salected from Table 4.4-1, for the Tendon Physical Condition Test.

2. Af ter detensioning, one random wire shall be removed from selected tendons shown in Table 4.4-2. The wires shall be visually inspected for corrosion, pitting, and other signs of deleterious changes..

3. Af ter visual inspection, three samples shall be taken from the pulled wire (one at each end and one from the middle) and subjected to tensile test. The acceptance criteria shall stipulate no failure below the guaranteed ultimate strength of all samples.

'. Af ter inspection, the tendons shall be retensioned to the lif t-off stress l

level observed before detensioning. Any changes in the shin thickness shall be recorded.

Y' sal \E0 4-35b

Change Request No. 11

c. Tendon Anchorage Assembly Inspection The tendon anchorage assemblies and the associated hardware (bearing plates, streseing washers, stressing shims, button heads, etc.) of all selected tendons shall be visually inspected for signs of corrosion, off-size or cracked button heads, cracks, missing wires, and broken wires. The concrete around the tendon anchorage area shall be inspected for crack width and the general cracking pattern. The acceptance criteria shall be that all crack widths greater than 0.010 inch shall be recorded and reported for evaluation and resolution, and any l crack width greater than 0.050 inch shall be cause for investigation to determine the amount of structural impairment upon the reactor building and its continued structural integrity,

d. Inspection of Corrosion Protection System.

The inspection of Corrosion Protection System shall be based on visual observations and tests. The procedure for removing the grease in order to make visual inspection shall insure that no damage to the steel (by scratching) and no increase of corrosion effects shall occur during grease removal even under most unfavorable conditions.

Thermal degradation of the filler grease is not anticipated. The system is designed to remain stable in the range of temperature likely to be encountered during the life of the unit.

I Representative grease sample shall be taken from each end anchorage of the selected tendons specified in Table 4.4-2 and tested for chloride, sulphide, nitrate, and moisture content. The acceptance criteria shall limit the amount of any one of the contaminants to 10 ppm and the ratio of water / dry weight shall not exceed 5%.

To uncover possible voids in the trumpet , the grease pump hose shall be inserted into the trumpet through a hole in the split bearing washer and heated grease l

4-35c 15 c 9 1 t,0

.;ange Request No. 11 pumped until it starts flowing from the hole on the opposite side of the washer.

A similar procedure shall be used in refilling the tendon cap.

4.4.2.1.h Reporting Procedure The failure of the tendon or parts of tendon and its anchorage to meet the criteria of this Inservice Tendon Surveillance Program shall be treated as an l indication of abnormal degradation of the containment structure, and it shall be reported to the U.S. Nuclear Regulatory Commission in accordance with Regulatory Guide 1.35. The initial report shall be made within 10 days af ter the completion of the tests and the detailed report may follow within 90 days after the completion of the tests.

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'. L. Age Request No. 11 TABLE 4.4-1 SELECTED TENDONS AND CORRESPONDING INSPECTION PERIODS

1. Dome Tendons Inspection Period Tendons 1 D-101, D-ll6, D-201, D-220, D-301, D-316 2 D-102, D-ll7, D-202, D-219, D-av2, D-317 3 D-103, D-118, D-203, D-218, D-303, D-318 4, 7, 10 D-116, D-220, D-316 5, 8 D-102, D-202, D-302 6, 9 D-ll8, D-218, D-318

2. Vertical Wall Tendons Inspection Period Tendons 1 V-16, V-2 7, V-61, V-66, V-158 2 V-24, V-48, V-72, V-97, V-119 3 V-18, V-31, V-55, V-105, V-138 4, 7, 10 V-16, V-86, V-158 5, 8 V-24. V-48, V-119 6, 9 V-18, V-105, V-138

3. Hoop Tendons Inspection Period Tendons 1 H-13-028, H-13-034, H-13-046, H-24-009, H-24-013, H-35-010, H-35-028, H-51-012, H-51-033, H-62-010 2 H-13-029, H-24-010, H-24-019, H-35-011, H-35-029, H-46-020, H-4 6-024, H-51-010, H-51-034, H-62-011 3 H-24-011, H-24-028, H-35-009, H-46-018, H-46-022, H-2h-020, H-51-011, H-51-035, H-62-012, H-62-028 4, 7, 10 H-13-046, H-24-018, H-51-033 5, 8 H-46-024, H-51-03h, H-62-011 6, 9 H-24-020, H-51-Oll, H-51-035 q lgJU ,7 4

i'd 4-36 a

Chans Request No. 11 TABLE 4.4-2 TENDONS SELECTED FOR TENDON PHYSICAL CONDITION TEST TENDON LOCATION Inspection Pe riod Dome Wall Hoop 1 D-301 V-2 7 H-35-010 2 D-117 V-119 H-13-029 ,

3 D-103 V-18 H-46-018 4 D-220 V-86 H-51-03 3 5 D-302 V-48 H-46-024 6 D-218 V-105 H-51-011 7 D-116 V-158 H-13-046 8 D-202 V-24 H-62-011 9 D-318 V-138 H-24 -020 10 D-316 V-16 H-24 -018 4

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4-36b

. s..ange Request No. 11 No. & Rebar Orientation Azimuth Elevation 58 Hoop 108 446'-0" 58 Vertical 1080 446 '-0" 59 Hoop 2450 446'-0" 59 Vertical 245 446'-0" 60 Hoop 352 446'-0" 60 Vertical 352 446 '-0" 129 Hoop 800 446 '-0" 129 Vertical 00 0 446'-0" 130 Hoop 3200 446'-0" 130 Vertical 320 0 446 '-0" 61 Hoop 108 0 452'-0" 61 Vertical 108 0 452'-0" 62 Hoop 245 452'-0" 62 Vertical 245 452'-0" 63 Hoop 3520 452'-0" 63 Vertical 352 452'-0"

2. The strain gage readings from each inspection shall be checked against the previous inspection readings and the duration recorded. Any deviation of strain readings, for the same strain gages, greater than 0.0004 in/in or % 11,500 psi. shall be reported to the Station / Unit Superintendent for evaluation and resolution.

C. Visual Inspection

1. Crack pattern charts shall be made during each ring girder inspection period. The areas of the concrete which shall be inspected and charts recorded are as listed below and as shown in Figure 4.4-1. The data shall be recorded on the appropriate Figure; refer to Figures 4.4-2, 4.4-3, 4.4-4 and 4.4-5.

Whitewash Areas Area Centerline Area Centerline No. Elevation Azimuth 131 445'-0"

• 20 120 445'-0" 175 132 445'-0" 320 133 445'-0" 3500 The Whitewash Areas are 6 ft - 0 in wide by 12 f t - 0 in, high.

2. The charts from each inspection shall be checked against the previous inspection charts. Any crack widths greater than 0.010 inch shall be reported to the Station / Unit Superintendent for )

evaluation and resolution.

}bo) e 4-36d

Jhange Request No. 11

k. a progress and status report en any items identified as requiring additional information during the operating license review or during the startup of the plant, including items discussed ir the AEC's safety evaluation, items on which additional infor=ation was required as conditions of the license and items identified in the licensee's startup report.

c. Special Test Reports Special test reports shall be prepared and submitted to the Director, Directorate of Licensing, USAEC, as follows:

Tests Submittal Dates

1. Containment Structural Integ- Within 6 months after rity Test completion of test

2. Containment Integrated Leak Within 6 months after Rate Test completion of test

3. Inservice Inspection Program Within 6 months after five years of operation

h. Tendon Surveillance Program Within 3 months after l performance of surveillance program.

E O 1 I e Ju/ is3 6-13