ML19309A127
| ML19309A127 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/06/1972 |
| From: | Schwencer A US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Davis E SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 8003260845 | |
| Download: ML19309A127 (3) | |
Text
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MV 61972 Docket No. 50-312 i
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Mr. E. K. Davis, General Counsel
,,g Sacramento Municipal Utility District y5 6201 S Street, P. O. Sox 15830 7?n #:
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Dear Mr. Davis A
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On the basis of our continuias resiew of the Final Safety Analysis Report ~. R.3$
for the Ranebo seco Nuclear Genersting Station, we find that we need
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4, In order to maintain our licensing review schedule, we will need a completely adequate response by November 20, 1972. Please inform us within seven G) days after receipt of this letter of your confirmation of the.
schedule or the date you will be able to meet. If you cannot meet sur [ [ Y specified date or if your reply is not fully responsive to our requests, it is highly lik.ly that the overall schedula for completing the licenstag.
review for this project will have.to be extended. Since reassignmenf ef the staff's efforts vill require sempletion df,the new as'signment prio1E % ~ M 2 7 ~
returning to this projeetf the estemt of entenstan~will moet likely be greater ~
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^".Q than the extent of delay in your response.
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Request for. Additional Information
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IEQUESP FO*t ADDITIONAL INFORMAT 1
KANCHO SECO NUCLEAR GENERATING STAAf0N DOCKET NO. 50-312 3.0 REACT 0_R 3.7 Supplement the response to Request 3.7 by clarifying your intention to conduct prototype preoperational vibration testing for Rancho Seco in the event Oconee 1 is not qualified as a prototype plant, in accordance with the requirements of Safety Guide #20.
4.0 REACTOR COOLANT SYSTDi 4.26 Complete the response to Request 4.26 by providing a description of the method used to measure the displacement amplitudes and the acceptance criteria that will be implemented to confirm whether the amplitude escceeds allowable limits. The application of such measurement and criteria is required for the piping and piping i
restraints where significant vibratory response are detected during the initial phase of piping vibration test.
4.28 Supplement the response to Request 4.28 by identifying the extent of conformanceofthepresentpipewhipprotectionwitgtheprotection provided by the following AEC criteria:
The piping breaksshoulgbe postulated to occur at the following locations in each piping run or branch run:
(a) the terminal ends, and (b) any intermediate locations between terminal ends where the primary plus secondary stress intensities Sn (circumferential or longitudinal) derived on an elastica 11y calculated basis under the loadings associatedwighseismiceventsandoperationalplantconditions3 exceeds 2.0S, for ferritic steel, and 2.4S for autenitic steel, and m
(c)anyintermediatelocationsgetweenterminalendswherethe cumulative usage factor (U) derived from the piping fatigue analysts and based on all normal, upset, and testing plant conditions exceeds 0.1, and
- 1. Piping is a pressure retaining component consisting of straight or curved pipe and pipe fittings (e.g., elbows, tees, and reducers)L
- 2. A piping run interconnects components such as pressure vessels, pumps and valves that may act to restrain pipe movement beyond that required for design thermal displacement. A branch run differs from a piping run only in that it originates at a piping intersection, as a branch of the main pipe run.
- 3. Operational plant conditions include normal reactor operation, upset conditions (e.g., anticipated operational occurrences) and testing conditions.
- 4. S is the design stress intensity as specified in Section III of the ASME o
Boiler and Pressure Vessel Code, " Nuclear Power Plant Components."
- 5. U is the cumulative usage factor as specified in Section III of the ASME f
Boiler and Pressure Vessel Code, " Nuclear Power Plant Components."
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e 7 s, 2-(d) at intermediate locations in addition to those determined by 1(b) and 1(c) above, selected on a reasonable basis as necessary to provide protection. As a minimum, there should be two intermediate locations for each piping run or branch run.
For reducing the probability of pipe failure occurrence at such locations where the piping protection is required under AEC criteria but is excluded in your present design, a supplemental inservice inspection should be submitted which consists of 100 percent inspection of.the circumferential welds at these locations during each inspection period as specified in Section XI of the current ASME code.
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