ML18010A888
| ML18010A888 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/09/1992 |
| From: | Le N Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-M84620, NUDOCS 9211130346 | |
| Download: ML18010A888 (9) | |
Text
Docket No. 50-400 November 9, 1992 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 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 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.
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 LA:
1:DRPE PM:PD21:DR PD:PD2 PE NAME DATE SLW le ll /'I /92 NBLe:tms
) /6/92 am I /
/92 FILENAME:
HAR84620.MTS
(.I 9222130346 '922209 1
I PDR ADQCK 05000400 P
PDR)
4 a
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 State 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 Mr. 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
DISTRIBUTION' Docket.Fi:le~
NRC/Local PDRs PD II-1 Reading T. Hurley F. Hiraglia 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 H.
E. Hayfield J,
Ramsey S.
Peterson A.
Lee T. Koshy R. Schaaf ACRS (10)
L. Plisco, EDO E. Herschoff, Region II cc:
Licensee 5 Service List
v
NRC/CP&L Meeting October 7, 1992 ENCLOSURE 1
NAMES Jeff Jacobson Frank Orr Robert C. Jones Thomas Scarbrough Cliff Doutt Larry Costello William M. Pearyhouse David McCarthy C.
S. Hinnant Talmage Clements Lewis Rowell E.
G. Adensam Terence L. Chan Mickey Hamby M. C.
Shannon M.
E. Mayfield Tommy Le Jack Ramsey Sheri Peterson L. L. Gundrum J.
R. Houghton Don Woodlan Arnold Lee Thomas Koshy Robert Schaaf ORGANIZATIONS NRR/DRIS NRR/SRXB NRR/SRXB NRR/DET/EMEB NRR/HIC8 CP&L CP&L CP&L CP&L CP&L CP&L NRC/NRR/PD2-1 NRR/EMEB CP&L NRC/RES/HARRIS OEDO NRC/NRR/PD2-1 NRR/DORS/OEAB NRR/DRPW/P04-1 AEOD/DRS/ROAB AEOD/DRS/TPAB TU Electric NRR/EMEB NRR/EAB NRR/DRPW/PD2-2
ENCLOSURE 2
'AGENDA INTRODUCTION AND PURPOSE D.
MCCARTHY MECHANICAL DESIGN B. PEAWHOUSE ELECTRICAL / ILC DESIGN L.
COSTELLO POST-MODIFICATION TESTING B.
BOISVERT
SUMMARY
D.
MCCARTHY S.
HINNANT
PURPOSE TO BRIEF THE NRC STAFF AND ADDRESS ALL QUESTIONS OR CONCERNS RELATED TO THE DESXGN DETAXLS FOR THE SAFETY IMECTXON ALTERNATE MINIFLOW MODIFXCATION PLANNED FOR THE CURRENT REFUELING OUTAGE AT THE SHEARON HARRIS NuCLEAR POWER PLANT.
~
~
e e
Alternate Miniflow S stem P
M difi tion Testin 1}
H dr t
icTe tin 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}
Post Modifica ion Testin A)
M in nan S rveillance 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)
M difi i n Acce ance Te 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 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}
Perio i
T 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.