ML17256B029
| ML17256B029 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/26/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0916, NUREG-0916-ERR, NUREG-916, NUREG-916-ERR, NUDOCS 8206110182 | |
| Download: ML17256B029 (4) | |
Text
~gll REPy
+4 0
0O I
~g I
I
~
~/+
0
/p +**+'+
't:
I UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 May, 26, 1982 ERRATA SHEET for NUREG-09l6 SAFETY EVALUATION REPORT RELATED TO THE RESTART OF R.E.
GINNA NUCLEAR POWER PLANT Please replace page 9-3 with the attached corrected page."
Item 20 was inadvertently omitted from this page.
DIVISION OF TECHNICAL INFORMATION AND DOCUMENT CONTROL C
N
', PDR, ADOCK 05000244,,'-;
0 o
(
g 14.
15.
Confirm by test that the modified letdown system isolation functions properly and submit, within six months, a detailed design description.
(Section 6.4)
Confirm by test that the wide range pressurizer pressure transmitter functions properly and submit,.within six months, a detailed design description.
(Section 6.8) 16.
Perform fiber optic inspections during the intermediate outage of the tubes in Row 45 of the 8-steam generator hot leg, (Section 5.5.8.4) 17.
Submit, within"six"months, a detailed design description of the Loose Parts Monitoring System.
(Section 5.5.6) 18.
Within six months, review and.identify potential transients and accident scenarios that could provide relatively stagnant. flow conditions in a coolant'oop, and examine, the effect of the operator taking actions which would draw'he cold water into the vessel.
For these scenarios, review and modify procedures and train operators as necessary. to prevent or minimize the flow of, cold water into the vessel.
(Section 3.5) 19.
In the long term, include an evaluation of the scenarios identified above in the overall resolution of the pressurized thermal shock issue.
Modify equipment, procedures and operator training in accor-dance with the resolution of that issue.
(Section 3.5) 20.
Within six months, determine the criteria which should be provided in the steam generator tube rupture procedures for deciding when to discontinue the use of the.main condenser in favor of the atmospheric steam dump.
I Ginna Restart SER 9-3
a V
g 1
'E A
9 C
< J