ML20009D748
| ML20009D748 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/10/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-16, PLA-868, NUDOCS 8107240317 | |
| Download: ML20009D748 (3) | |
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e PP&L TWO NORTH NINTH STREET ALLENTOWN, PA.18101 PHONE: (215) 770-5151 NORMAN W. CURTIS p
Vice President-Engineenng & Construction Nuclear j
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JUL 101981
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.Mr. Boyce H. Grier, Director
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U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION IE BULLETIN 80-16 ER 100450 FILE 842-3 DOCKET NOS. 50-387 PLA-868 AND 50-388
Dear Mr. Grier:
The following information completes our response to IE Bulletin 80-16,
" Potential Misapplication of Rosemount Inc. Models 1151 and 1152 Pressure Transmitters with either
'A' or 'D' Output Codes." This letter supplements our previous responses in PLA-548 and PLA-621 dated September 30, 1980 and January 28, 1981.
IE Bulletin actions to be taken:
1.
The subject pressure transmitters have been installed at Susquehanna SES in safety-related applications. Only Model 1151 pressure transmitters are involved.
2.
The pressure transmitters identified in item I were analyzed to determine worst case input pressures during normal operation and accident conditions.
Potential excessive over pressure conditions were found for seventeen of these pressure transmitters. No excessive reverse pressure conditions were identified. The attached table provides specific information requested by the bulletin for each of the affected pressure transmitters.
3.
Unit 1 pressure transmitters listed in the attached table will be replaced
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prior to Unit I fuel load.
St itable replacements will be obtained for Unit 2 transmitters prior to Unit 2 fuel load.
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s 8107240317 810710 PDR ADOCK 05000387 O
PDR II P E N N SY LV A NI A POWER & LIG H T CO MP ANY
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5 Mr. Boyce H. Grier Page 2
. July 1, 1981 Estimated manpower expended on IE Bulletin 80-16:
a) Report preparation and review 2000 nanhours b) Corrective actions 1500 manhours Total 3500 manhours
- Very truly yours, f%.
l N. W. Curtis Vice President-Engineering &' Construction-Nuclear RMH/mks.
Attachment l
cc: Director Division of Reactor Construction Inspection l
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 i
Mr. G. G. Rhoads l
U.S.-Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655 l
Mr. L. D. Narrow
(
'U.S. Nuclear Regulatory Commission 631 Park Avenue l
King of Prussia, PA 19406 i
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MAX ROSEMOUNT INSTRUMENT MODEL TAG SERVICE CORRECTIVE CALIBRATION MODEL NUMBER NUMBER DESCRIPTION FUNCTION ACTION RANCE RANCE g
1151GP6A52MB PT-E32-IN050 MSIV-LCS Reactor Press.
E, All Note 1 0-100 PSIG 0-100 PSIG 1151GP6A52MB PT-E32-IN058 MSIV-LCS Reactor Press.
V Note 1 0-100 PSIC 0-100 PSIC ll51GP6A52MB PT-E32-lN060 MSIV-LCS Reactor Press.
B, I, AII Note 1 0-100 PSIG 0-100 PSIG ll51GP6A52MB PT-E32-lN055 MSIV-LCS Outlet ilDR Press.
B Note 1 0-100 PSIG 0-100 PSIG 1151GP6A52MB PT-E32-IN061B MSIV-LCS INBD Steam Press.
B,I Note 1 0-100 PfIG 0-100 PSIG 1151GP6A52MB PT-E32-IN061F MSIV-LCS INBD Steam Press.
B, T Note 1 0-100 PSIC 0-100 PSIG 1151GP6A52MB PT-E32-111061K MSIV-LCS INBD Steam Press.
B,1 Note 1 0-100 PSIG 0-100 PSIG 1151GF6A52MB PT-E32-lN061P MSIV-LCS INBD Steam Press.
B, I Note 1 0-100 PSIG 0-100 PSIC ll51APSA52MB PT-E32-IN056 MSIV-LCS Outlet ilDR Press.
B Note 1 0-30 PSIA 0-750 IrniC ll51AP5A22T0003PB PT-E32-lN051B MSIV-LCS INBD Steam Press.
I, V Note 1 30 inlig-10PSIG 0-750 ItnJC 1151AP5A22T0001PB PT-E32-IN051F MSIV-LCS INBD Steam Press.
I, V Note 1 30 inHg-10PSIG 0-750 ItavC 1151AP5A22T0003PB PT-E32-lN051K MSIV-LCS INBD Steam Press.
I, V Note 1 30 inHg-10PSIC 0-750 INWC ll51AP5A22T0003PB PT-E32-IN051P MSIV-LCS INBD Steam Press.
I, V Note 1 30 inlig-10PSIG 0-750 INWC 1151AP5A22MB PT-15728A Drywell Pressure I
Note 2 0-20 PSIA 0-750 IrnJC ll51AP5A22MB PT-15702 Suppression Pool Pressure I
Note 2 0-20 PSIA 0-750 IfnJC 1151APSA22MB PT-25728A Drywell Pressure I
Note 2 0-20 PSIA 0-750 Itn4C ll51AP5A22MB PT-25702 Suppression Pool Pressure I
Note 2 0-20 PSIA 0-750 INWC Blower Control Logic Functions:
B
=
Valve Control Logic V
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Alarm Trip Unit Input (11 = liigh)
A
=
Indicator I
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Note 1:
Transmitters will be replaced with acceptable transmitters from SSES Unit 2 per FDDR KR2-301-3.
Note 2:
Transmitters will be replaced per disposition, NCR-5988.
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M/X PROGESS CONDITION i
11AX 110 DEL f
RANGE NORt1AL ACCIDENT 140 PSIG 1020 PSIA 1250 PST(;
140 PSIC 1020 PSIA 1250 PSIG 140 PSIG 1020 PSIA 1250 PSIC 140 PSIG 985 PSIA 1250 PSIG 140 PSIG 1020 PSIA 1250 PSIG i
140 PSIG 1020 PSIA 1250 PSIG 140 PSIG 1020 PSIA 1250 PSIG I
140 PSIG 1020 PSIA 1250 PSIG 38 PSIA 985 PSIA 1250 PSIG 38 PSIA 1020 PSIA 1250 PSIG s
38 PSIA 1020 PSIA 1250 PSIG
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38 PSIA 1020 PSIA 1250 PSIG
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38 PSIA 1020 PSIA 1250 PSIG 38 PSIA 1.5 PSIC 60 PSIA y
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38 PSIA 1.5 PSIG 45 PSIA
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1.5 PSIG 60 PSIA 38 PSIi 1.5 PSIG 45 PSIA 5
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