ML19320C022
| ML19320C022 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/08/1980 |
| From: | Novarro J LONG ISLAND LIGHTING CO. |
| To: | Snaider R Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-10, REF-GTECI-RV, RTR-NUREG-0619, RTR-NUREG-619, TASK-A-10, TASK-OR SNRC-484, NUDOCS 8007150655 | |
| Download: ML19320C022 (3) | |
Text
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.e. wwevasu*svaah-p LONG ISLAND LIGHTING COM PANY L124'O 4,4meramww GHOREMAM NUCLEAR POWER STATION P.O. BOX 618, NORTH CourwTRY ROAf3
- WADING RIVER. N.Y.11792 July 8, 1980 SNRC-484 Mr. Richard Snaider Generic Issues Branch U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Comments on NUREG-0619 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322
Dear Mr. Snaider:
In response to NRC letter dated June 6, 1980 from D. G. Eisenhut to A. W. Wofford, we have reviewed NUREG-0619, " BUR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking" and submit the following comments:
In T
" Routine Inspection Intervsis" on page
.4, 18, the routine PT requirement for plants with triple sleeves, two piston ring seals and clad removal should be modified to read "PT shall be performed if UT or visual examination discloses discontinuities which need corrective action" rather than that specified in footnote 2.
See marked-up page attached. 'Although leakage with the two piston ring seal is not antici-pated, a significant deterioration of the seal could be an additional condition to require PT examination.
This modification is based upon technical considerations coupled with our ongoing commitment to minimize the man-rem exposures to plant personnel.
We consider that the results of the General Electric tests showed the adequacy of this design and concur with the hTC Staff conclusion that, "With regard to the triple sleeve sparger design,...
the test results demonstrate that it should be effective
'/ o 04-in reducing thermal c s
blend radius areas." ycling of feedwater nozzle bore and Furthermore, G.E. predicted no f/j crack initiation in 40 years with full power feedwater temperature of 420 F and leakage held to a maximum of ADD' $5 5"5 1 gpm.
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Mr. Richard Snaider July 8, 1980 Re: _ Comments on NUREG-0619 Page 2 Periodic UT examination has been permitted to monitor possible extension of cracks in the cladding in PWR steam generators.
Crack propagation in this service is'also considered unlikely and the UT method was considered acceptable.
Some steam generators have cast components which makes UT examination somewhat difficult to perform.
On the other hand, the feed-water nozzles are vrought and with the cladding removed, ultrasonic examination of the nozzles can be performed with relative ease.
Accordingly, we consider.that an aggressive UT examination method such as planned for Shoreham, subject to the restric-tion noted above, is sufficiently adequate.
We a7preciate this opportunity to provide our comments.
Should you have any questions on the above matter please do not hesitate to contact this office.
Very truly yours,
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{J.P.Novarro, o
Project Manager Shoreham Nuclear Power Station LG/cc Attachment cc:
J. Higgins
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TABLE 2 ROUTINE INSPECTION INTERVALS Inspection Interval (refueling cycles or start-uo/ shutdown cycles)
Visual Inspection Routine PTI Leak Test 3 Configuration UT of Spargeri Interference fit, clad 4 1
2 2 (or 30 F V Welded, clad 8 2
2 4 (or 60)# ' '
2 Single sleeve, single 2
4 4 (or 60)1 2
piston ring seal, clad removeds g
Oyster Creek & Nine Mile
.2 4
6 (or 90)
None Point (clad removed, significantly modified spargers installed)
Weldea, clad removed 2
4 6 (or 90)#,' y 4
(spargers have top-mounted elbows)6 Triple sleeve plants with 2
4 9 (or 135) 4 two piston ring seals, clad removeds 1 Visual inspection of ficw holes and welds in sparger arms and sparger tees.
2To be performed even if the UT and Leak Test Results are satisfactory.
3In-vessel, physical leak test (see section 4.3.2.4).
4The present inspection interval began at the last inspection during which an interference - fit sparger was removed for PT inspection.
5Next refueling after 30 startup/ shutdown cycles, but not later than tne second refueling cycle after the previous PT inspection.
8The present inspection intervel began at the last PT inspection of accessible portions of the nozzle.
7 Accessible areas only 8The present inspection interval began when cladding was removed and the triple sleeve or single sleeve piston ring spargers were installed.
To be. pe.c ie r m e.d
.2 UT cc vi tea.\\
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