ML18022A909
| ML18022A909 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/09/1992 |
| From: | Le N Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18010A891 | List: |
| References | |
| TAC-M84620, NUDOCS 9211160196 | |
| Download: ML18022A909 (22) | |
Text
November 9, i992 Docket No. 50-400 LICENSEE:
0@rolina Power
& Light Company FACILITY:
Shearon Harris Nuclear Power Plant, Unit 1
SUBJECT:
MEETING
SUMMARY
OF MARCH 30,
- 1992, REGARDING MODIFICATION OF THE SAFETY INJECTION ALTERNATE MINIFLOW SYSTEM (TAC NO. M84620)
This refers to the subject meeting conducted at the NRC Headquarters in Rockville, Maryland, on October 7, 1992.
The purpose of the meeting was for Carolina Power
& Light Company to brief and provide responses to the staff questions 'related to the design details for the Safety Injection Alternate Miniflow (AMF) system modification planned for the current refueling outage at the Shearon Harris Nuclear Power Plant.
Enclosure 1 is the list of attendees, and Enclosure 2 contains copies of material used during the meeting.
The licensee stated that the planned modification will:
(1) provide the same deadheading protection for the Charging/SI
- pumps, (2) not affect the high-head SI system ability to protect the core, and (3) remove weak links that were previously identified in LER 91-08.
Highlights of the discussion included detailed de ign regarding planned piping
- changes, hardware
- changes, logic changes, and instrumentation and control changes to the AMF system.
In addition, post-modification testing, procedural
- changes, and operator training regarding the modification were also. discussed at the meeting.
The licensee committed to provide details of the AMF modification package and additional information related to design documents for further staff review.
Original signed by
Enclosures:
1.
List of Attendees 2.
Meeting Materials cc w/enclosures:
See next page Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation OFC NAME DATE LA:
1:DRPE SHt le ll 9 92 PM: PD21:DR NBLe:tms
) /6/92 PD:PD2 PE am
( /
/92 FILENAME:
HAR84620.MTS
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eiys V
Mr. R. A. Watson Carolina Power
& Light Company Shearon Harris Nuclear Power Plant, Unit 1
CC:
Mr. H.
Ray Starling Manager - Legal Department Carolina Power
& Light Company P. 0.
Box 1551
- Raleigh, North Carolina 27602 Resident Inspector/Harris NPS c/o U. S. Nuclear Regulatory Commission Route 1,
Box 315B New Hill, North Carolina 27562 Mr. Gerald E. Vaughn, Vice President Harris Nuclear Project Harris Nuclear Plant P. 0.
Box 165 New Hill, North Carolina 27562
. Mr. H. A. Cole Special Deputy Attorney General State of North Carolina P. 0.
Box 629
- Raleigh, North Carolina 27602 Public Service Commission
~'tate of South Carolina P.O.
Drawer 11649
- Columbia, South Carolina 29211 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street Suite 2900 Atlanta, Georgia 30323
'r.
C.
S. Hinnant Plant General Manager Harris Nuclear Plant P. 0.
Box 165 New Hill, North Carolina 27562 Mr. Dayne H. Brown, Director
~Division of Radiation Protection N.
C. Department of Environmental, Commerce
& Natural Resources P. 0.
Box 27687
- Raleigh, North Carolina 27611-7687 Mr. R.
B. Starkey Vice President Nuclear Services Department Carolina Power
& Light Company P. 0.
Box 1551
- Raleigh, North Carolina 27602
I
NRC/CP&L Heeting October 7, 1992 ENCLOSURE 1
NANES Jeff Jacobson Frank Orr Robert C. Jones Thomas Scarbrough Cliff Doutt Larry Costello William H. Pearyhouse David HcCarthy C.
S. Hinnant Talmage Clements Lewis Rowell E.
G. Adensam Terence L. Chan Hickey Hamby M. C.
Shannon H.
E. Hayfield Tommy Le Jack Ramsey Sheri Peterson L. L. Gundrum J.
R. Houghton Don Woodlan Ar'nold Lee Thomas Koshy Robert Schaaf ORGANIZATIONS NRR/DRIS NRR/SRXB NRR/SRXB NRR/DET/EHEB NRR/HICB CP&L CP&L CP&L CP&L CP&L CP&L NRC/NRR/PD2-1 NRR/EHEB CP&L NRC/RES/HARRIS OEDO NRC/NRR/PD2-1 NRR/DORS/OEAB NRR/DRPW/PD4-1 AEOD/DRS/ROAB AEOD/DRS/TPAB TU Electric NRR/EHEB NRR/EAB NRR/DRPW/PD2-2
I'~
fNCLOSURE 2 AGENDA INTRODUCTION AND PURPOSE D.
MCCARTHY MECHANXCAL DESIGN B. PEAVmOUSE ELECTRICAL /
?ELC DESIGN L.
COSTELLO POST-MODXFXCATION TESTXNG B.
BOXSVERT
SUMMARY
D.
MCCARTHY S.
HXNNANT
PURPOSE TO BRIEF THE NRC STAFF AND ADDRESS ALL QUESTIONS OR CONCERNS RELATED TO THE DESIGN DETAILS FOR THE SAFETY INJECTION ALTERNATE HINIFLOW MODIFICATION PLANNED FOR THE CURRENT REFUELING OUTAGE AT THE SHEARON HARRIS NUCLEAR POWER PLANT.
ifi i
T
'n
'))
H r
i T
in ofpi in Hydrostatic testing of the piping changes will be in accordance with ASME Section 11 requirements.
Valves used as hydro boundary valves will be cycled and verified to be operable after completion of the hydrostatic test.
2)
P s M
ifi i nT sin A)
IVI in n
rv ill nc T
in B)
Instrument loop procedures will be completed on the Wide Range RCS Pressure Loops (P-402 5 P-403) prior to Post Modification testing.
This testing will include all components up to the valve opening and closing contacts.
IVI ifi 'A ce n
T in 1)
Testing will be performed to verify all logic functions of the motor operated valve actuation.
2)
Testing will be performed to verify that relay K636 (relay that is no longer used in this function) still is operational.
3)
Flow through Alternated Miniflow Orifice will be verified using Ultrasonic Flow IVleasuring equipment (Transit-Time Unit designed for use with clean water).
4)
Flow through all piping will be witnessed by Nuclear Engineering Department personnel for the purpose of documenting any abnormal pipe movements or flow noise.
3)
P ri i
T i
Periodic testing will be conducted on the installed valves.
Present testing will be revised to correspond to the modified valve operation.
Also MOV testing will be performed in accordance with Generic Letter 89-10.
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++*++
e UN'ITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 November 9, 1992 Docket No. 50-400 LICENSEE:
Carolina Power 8 Light Company FACILITY:
Shearon Harris Nuclear Power Plant, Unit 1
SUBJECT:
MEETING
SUMMARY
OF MARCH 30,
- 1992, REGARDING MODIFICATION OF THE SAFETY INJECTION ALTERNATE MINIFLOM SYSTEM (TAC NO. M84620)
This refers to the subject meeting conducted at the NRC Headquarters in Rockville, Maryland, on October 7, 1992.
The purpose of the meeting was for Carolina Power 8 Light Company to brief and provide responses to the staff questions related to the design details for the Safety Injection Alternate Miniflow (AMF) system modification planned for the current refueling outage at the Shearon Harris Nuclear Power Plant.
Enclosure.1 is the list of attendees, and Enclosure 2 contains copies of material used during the meeting.
The licensee stated that the planned modification will:
(1) provide the same deadheading protection for the Charging/SI
- pumps, (2) not affect the high-head SI system ability to protect the core, and (3) remove weak links that were previously identified in LER 91-08.
Highlights of the discussion included detailed design regarding planned piping
- changes, hardware
- changes, logic changes, and instrumentation and control changes to the AMF system.
In addition, post-modification testing, procedural
- changes, and operator training regarding the modification were also discussed at the meeting.
The licensee committed to provide details of the AMF modification package and additional information related to design documents for further staff review.
Enclosures:
1.
List of Attendees 2.
Meeting Materials cc w/enclosures:
See next page Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
~OIUI U IO:
- Docket Fi1 e ~
NRC/Local-PDRs PD II-I Reading T. Hurley F. Miraglia J.
Ramsey J.
Partlow S.
Varga G. Lainas E.
Adensam N.
B.
Le S. Little OGC E. Jordan J.
Jacobson F. Orr R. Jones T. Scarbrough C. Doutt T.
Chan H. C. Shannon M.
E. Mayfield J.
Ramsey S. Peterson A. Lee T. Koshy R; Schaaf ACRS (10)
L. Plisco, EDO E. Merschoff, Region II cc:
Licensee 5 Service List
CAROLINA POMER &
L IGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT MEETING
'ITH THE NRC ON SAFETY INJECTION ALTERNATE MINIFLOW MODIFICATION OCTOBER 7, 1992
AGENDA INTRODUCTION AND PURPOSE MECHANXCAL DESIGN D.
MCCARTHY B. PEAVVHOUSE ELECTRICAL / I&C DESXGN POST-MODIFXCATION TESTING
, L.
COSTELLO B.
BOISVERT
SUMMARY
D.
MCCARTHY S.
HXNNANT
PURPOSE TO BRIEF THE NRC STAFF AND ADDRESS ALL QUESTIONS OR CONCERNS RELATED TO THE DESIGN DETAILS FOR THE SAFETY INJECTION ALTERNATE MINIFLOW MODIFICATION PLANNED FOR THE CURRENT REFUELING OUTAGE AT THE SHEARON HARRIS NUCLEAR POWER PLANT.
0 Alternate Miniflow S stem Po t IVlodifi ti n Testin 1)
H dro tatic Testin of Pi in Hydrostatic testing of the piping changes will be in accordance with ASME Section 11 requirements.
Valves used as hydro boundary valves will be cycled and verified to be operable after completion of the hydrostatic test.
2}
Post Modification Testin A)
Maint nanc Surveill n e Te in Instrument loop procedures will be completed on the Wide Range RCS Pressure Loops (P-402 5, P-403) prior to Post Modification testing.
This testing will include all components up to the valve opening and closing contacts.
B) -
Modifica ion Acce tance Testin 1)
Testing will be performed to verify all logic functions of the motor operated valve actuation.
2)
Testing will be performed to verify that relay K636 (relay that is no longer used in this function) still is operational.
3)
Flow through Alternated Miniflow Orifice will be verified using Ultrasonic Flow Measuring equipment (Transit-Time
, Unit designed for use with clean water)
~
4)
'Flow through all piping will be witnessed by Nuclear Engineering Department personnel for the purpose of documenting any abnormal pipe movements or flow noise.
3)
Periodic Tes in Periodic testing will be conducted on the installed valves.
Present testing will be revised to correspond to the modified valve operation.
Also MOV testing will be performed in accordance with Generic Letter 89-1,0.
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SIXCHARGING PUMP PI 1C SAB 153B 2CS-V596SB-1 (1CS 192) 2CS V1 33SB 1 (1CS 191)
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