ML15223A792
| ML15223A792 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 04/08/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| GL-81-14, NUDOCS 8205030394 | |
| Download: ML15223A792 (5) | |
Text
APR IL 8 1982 DISTRIBUTION:
Docket File ORB#4 Rdg RIngram Gray File NRC PDR DEisenhut HOrnstein L PDR PWagner EBlackwood JTBeard Dockets Nos. 50-269, 50-270 OELD C%
and 50-287 AEOD IE ACRS-10 Mr. William 0. Parker, Jr.
3 Vice President - Steam Production Duke Power Company P. 0. Box 33189 422 South Church Street Charlotte, North Carlina 282421
Dear Mr. Parker:
We have reviewed your January 28, 1982 response to NRC Generic Letter 81-14 concerning seismic qualifications of auxiliary feedwater systems.
In order for us to complete our review, we need additional, clarifying information on the subjects discussed in the enclosed Request for Additional Information.
Since we have established a completion date for this review of September 30, 1982, we request that you provide the requested informa tion within 30 days of your receipt of this letter.
This reporting requirement is solely regarding the Oconee Nuclear Station; therefore, fewer than ten respondents are affected and OMB clearance is not required under P.L.96-511.
If you have any questions, please contact your NRC Project Manager.
Sincerely, XOIGI VL SI GNED BY 0. STIOLZ" John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional Information cc w/enclosure:
See next page 820 503O_
__Li SCORB#4:D RB#4:DL PNagner JS SURNAME DATE * * **......*.
NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Duke Power Company P. 0. Box 33189 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh,,North Carolina 27603 Oconee County Library 501 West Southbroad Street Walhalla, South Carolina 29691 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Regional Radiation Representative EPA Region IV 345 Courtland Street, N.E.
Atlanta, Georgia 30308 William T. Orders Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.
DeBevoise & Liberman 1200 17th Street, N.W.
Washington, D. C. 20036
Enclosure Oconee Nuclear Station SEISMIC QUALIFICATION OF THE AUXILIARY FEEDWATER SYSTEM REQUEST FOR ADDITIONAL INFORMATION Question 1: of Generic Letter 81-14 (GL 81-14) defines the auxiliary feedwater (AFW) system to be considered as:
(a) "The AFW system boundary from suction to oischarge (including the water source and heat sink) shall include those portions of the system required to accomplish the AFW system function and connected branch piping up to and includino the second valve which is normally closed or capable of automatic closure when the safety function is requireG."
(b) "The AFW system boundary shall also include any portion of branch piping that is structurally coupled to the AFW system boundary such that the seismic response of the branch piping transmits loads to the AFW system. As a minimum, this inclUces the branch lines outside the AFW system boundary to a point of three orthogonal restraints."
(c) "All mechanical and electrical equipment, piping (e.g.,
instrument air), conouits and cable trays, which are necessary or contain items which are necessary for the operation of the AFW system, shall also be considered."
(d) "In addition, the structures housing these systems and components shall be included."
-2 Clarify the extent to which your standby shutdown facility boundary, considered in your January 28, 1981 response letter, coincides with the boundary defined in GL 81-14, especially part (b) above.
Question 2:
Generic Letter 81-14 states:
(a) "We are also requesting that PWR licensees perform a walk-down of the non-seismically qualifieo portions of their AFW system.s to identify apparent ano practically correctable deficiencies that may exist."
(b)
"The results of any walk-down are requested within 120 days of receipt of this letter.
These results should include all ioentifieo ceficiencies and all corrective actions taken, or planned along with the scheoules for such."
Our review of your response to Generic Letter 81-14 indicates that this information has not been provided for those non-seismically qualified items of your emergency feedwater system. Clarify whether a walk-down was performed and provide the results of any walk-down performed.
-3 Question 3:
Generic Letter 81-14, Enclosure 1, Part B states:
"Where seismic qualification is indicated by leaving Table 1 blank, provide a description of the methodologies and acceptance criteria used to support your conclusion of seismic qualification, including: seismic analyses methods employed, seismic input, load combinations which include the SSE, allowable stresses, qualification testing and engineering evaluations performeo."
Our review of your response to Generic Letter 81-14 indicates that this information has not been provideo for power supplies, water and supply paths, and the initiation and control system of your standby shutdown facility. Please correct this deficiency.