ML20084H786
ML20084H786 | |
Person / Time | |
---|---|
Site: | Browns Ferry ![]() |
Issue date: | 05/17/1974 |
From: | Eric Thomas TENNESSEE VALLEY AUTHORITY |
To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
Shared Package | |
ML20084H779 | List: |
References | |
AO-BFAO-7427W, NUDOCS 8305050058 | |
Download: ML20084H786 (23) | |
Text
{{#Wiki_filter:_ TENNES"EE VALLEY THORITY CHATTANOOGA, t=NNESSEE 37401 M4y 17, 1974 40
$$ $[j Mr. John F. O' Leary, Director Directorate of Licensing Office of Regulation U.S. Atomic Energy Commission Washington, DC 20545
Dear Mr. O' Leary:
TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 1 - DOCKET NO. 50-259 - FACILITY OPERATING LICENSE DPR ABNORMAL OCCURRENCE REPORT BFAO-7427W The enclosed report is to provide details concerning 58 Hancock 1-inch 600-lb. forged stainless-steel globe valves which are utilized in systems whose design conditions exceed the vendor's pressure-temperature ratings for the valves and is submitted in accordance with Appendix A to Regulatory Guide 1.16, Revision 1, October 1973 This event occurred on Browns Ferry Nuclear Plant unit 1 on May 7, 1974. Very truly yours, g g
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TENNESSEE VALLEY AUTHORITY 8 r' 5 ') N"). h
. T E. F. Thomas 6 MAY201974 > 3 n mci; .wr Director of Power Production g ji z, Gideal ,
Enclosure ' CC (Enclosure): Mr. Norman C. Moseley, Director Region II Regulatory Operations Office, USAEC 230 Peachtree Street, NW., Suite 818 Atlanta, Georgia 30303 ( i ' L t I h ( t
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J 8305050058 740612 4d'GG ' PDR S ADOCK 05000239 ^^ PDR COPY SENT REGION M
ABNORMAL OCCURRENCE REPORT Report No.: BFAO-7427W Report Date: May 17, 1974 Occurrence Dato: May 7, 1974 Facility: Browns Ferry Nuclear Plant unit 1 Identification of Occurrence Fifty-eight Hancock 1-inch 600-lb. forged stainless-steel globe valves are utilized , in systems whose design conditions exceed the vendor's pressure-temperature ratings l for the valves. [
- r Conditions Prior to Occurrence i i
Browns Ferry Nuclear Plant unit 1 was in the final phases of the startup testing i program. The unit had been operated through the complete power range. On Tuesday, May 7, 1974, while the reactor was being brought up to power, the plant was notified by the TVA Division of Engineering Design of the potential deficiency described in the next paragraph. The. decision was made to bring the reactor to a cold shutdown condition to resolve a relief valve problem which was undergoing review as well as to investiage the problem covered by this report. Description of Occurrence As a result of a routine procedure by the Division of Construction, a computer identification check of unit 1 valves revealed a discrepancy involving the subject 1-inch globe valves. Investigation of the discrepancy disclosed that the original design conditions ag specified by TVA on its purchase order for these valves were 1,250 psi at 575 F. Theseconditionswereneverrepsedtoagreewith an amendment of the system design condition of 1,146 psi and 562 F. established by the NSSS vendor. This discrepancy was reported to AEC on Tuesday, May 7. Further investigation of systems to which these valves had been applied revealed thatanumberofthegevalveswereutilizedigsystemswhosedesignconditions are 1,326 psi at %2 F. and 1,250 psi at 575 F. Analysis of Occurrence When notified of the problem, the Division of Engineering Design tabulated a list of the affected unit 1 valves to determine the number and their location. This tabulation can be found in Appendix A of this report. The valves are installed in the sampling lines of the recirculation and core spray systems and are used as high-point vent valves in the recirculation system. Correct 1ve Action i It was the opinion of TVA that a stress analysis in accordance with ASME Section III design rules for class 2 valves would permit the vendor and TVA to upgrade the pressure-temperature ratings for the valves in question. The analysis was performed by the vendor (see Appendix C) and by TVA. The required primary pregsure j rating of the valves for the most severe design conditions of 1,326 psi at %2 F. is Pr= 800 psi (see sheet 1 of Appendix D). l
o- _,_ O Corrective Action (continted) The required minimum wall thickness calculated is t = .243" (reference sheet 2 of Appendix D).
- Minimum valve wall measurements were perfomed on ten of the 1-inch Hancock globe valves in unit 1 at four locations which had previously been established as the minimum wall areas. All valves are part of a lot. A description and tabulation of the wall thickness zreasurements are presented in Appendix 3 of this report.
The ten valves measured are identified by an asterisk in Appendix A. Verification that all the valve wall thickness measurements exceed the calculated min 4== wall thickness is shown in Appendix D. The analysis of the valve body, bonnet, and bolting was perfomed by the valve manufacturer, Dresser. Industries, and was verified by TVA, as described in Appendix D. Recommendation' The engineering verification program undertaken by TVA and Dresser proves conclusively that these valves are capable of being rated to 900 lbs. if care is taken to control the amount of grinding for marking and excessive indentation of the marking tool is' prevented. In any case, the valves more than meet the requirement for an Boo-lb. rating, which funy satisfies the most severe design conditions to which they are subjected in this plant. o Inaddition,thesevalveshavereceivedaroomtemperagurehydrostatictest at 3,000 psi, which is equivalent to 2,780 psi at 562 F. and would be the required test pressure for an 1,854 design pressure, or more than required for these valves. Based on the results of the engineering evaluation, TVA takes the position that these valves are fully qualified for the higher design conditions. I l i f 4 .
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- APPENDIX D su JECT PROJECT M. M. Bressler 5/10/74 C.OMPUTED BY DATE CHECKED SV OATE im! 5/11/74 4.0 MEASURED WALL TIIICKFSSSr:S Reference Appendix A, valve list for unit 1 There are 53 valves involved whose design conditions are 1326 pai .3 562F, and 5 valves at 1250 psi and 575F for unit 1. For units .2 & 3 the numbers are 55 and 5. From Table IV-3 of MIL-STD-105A, for a lot size of 41 to 65 units, the first sample size should be 7. A total of 10 valves were measured on unit I at four locations which had previously been established as the minimum wall areas. All thicknesses were or exceeded 0.287" which occurred at an area along the side of the branch which has been ground to '
provide a flat for marking. The maximum depth of marking does not exceed
.012". Assuming 0.015" as an absolute extreme, the minimum wall is 0.287 - 0.015 = 0.272" which is in excess of the required 0.243".
Appendix B describes the locations where the measurements were made, and tabulates the measured dimensions for the unit valves. 5.0 VERIFICATION OF VENDORS CALCULATIONS The calculations submitted by Dresser Industrial Valves have been checked. They are shown in Appendix C, pages 1-5. The valves on page 1 can he verified from page 1 of this Appendix. They indicate that these valves can be certified to 900# class. The bonnet-to-body joint has been checked by various methods. First an approximation was made assuming the bonnet to be a blind flange as shown on the next page. l l l
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DESIGN CONDITIONS GASKET and BOLTING CALCULATIONS l lrY.$*.*['[ )
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