ML19319D285
| ML19319D285 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/28/1977 |
| From: | Mazetis G Office of Nuclear Reactor Regulation |
| To: | Kovacs J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003130926 | |
| Download: ML19319D285 (2) | |
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1 RSB File SEP 2 81977 Siegel chron
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Decket No. 50-302.
MEMORANDUM F03: John Kovacs, Mechanical Engineering Branch.fDSS THRU:
T. M..Novak, Chief, Reactor Systens Benoch, DSS D
,FROM:.
._1. LG. R.- Mazetis',..Section5 Leader,: Reactor Systems Branch,1. SS '
SUBJECT:
REVIENOFCRYSTAL~ RIVER 3REQUESTFORRELIEFFRO'1ASME
" SECTION XI PUMP AND VALVE TESTING REQUIRENDITS (TAC-4E49)
'Je have revievied the Florida Po.cer and Light docur.ent en Crystal River 3 per your request for technical a:sistance. Cnclosed are cur coments on Enclosures 1 throuch 4 to this document. We have identified the content
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.cf the:n enclosures that are unacceptable and these for t:hich additional inferr.+.tfon should be obtained tefere a resition can he taken.
It shculd also be notec that our reytcw was limited to valves and pu m s in the systets that relate to ECCS.
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Reactor Systems Branch Comments Crystal River 3 Recuest for ASME Code Exceptions 1.
CFV-1, 3
.CFV-2, 4 DHV-1, 2 The staff position is that two check valves in series provide adequate isolation of a low pressure system from a high pressure system only if there are design provisions to permit leak testing of the check valves at least once every refueling outage. Therefore, not testing the check valves identified in the decay beat and core flood systems is unacceptable.
2.
CFV-2 & 4 The B,C categorization of these check valves in the core flood system should be reevaluated.
3.
Div-42 & 43 Insufdicient information is given to justify any departure frcm the ASME Code requirements for decay heat system valves DHV-42 & 43. The staff position is that specific radiation levels must be presented which would preclude leak testing.
In addition, design provisions for remote testing should be considered.
4.
DHV-4 & 5 Confirm that these two valves in the decay heat system are normally open and have their power removed.
The rationale for not leak testing these valves is not adequate since only one train is required by the station Technical Specifications to be available during shutdown.
5.
DHV-33 throuah DHV-36 Justification for not leak testing these valves in the decay heat system should be submitted.
6.
The valve listings in Enclosures 2 and 3 should distinguish between Category A and B valves and should specifically identify which valves will be leak tested in addition to operational tests.
7.
With regard to safety valves, the Crystal River 3 Technical Specifications state that safety valves will be-tested in accordance with Section XI of ASME Boiler and Pressure Vessel Code, 1974 Edition through summer 1975 Addenda.
In Enclosures 2 and 3 of the Florida Power and Light submittal the safety valves are specified as being tested at least once every 5 years in accordance with ASME PTC 25.2-1966.
Will the testing times scheduled and the number of valves to be tested also conform to the schedule in Table IWV-3510'of Section XI of-the ASME Code?
.