ML18018B529
| ML18018B529 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/14/1983 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Ray J Advisory Committee on Reactor Safeguards |
| References | |
| NUDOCS 8312270009 | |
| Download: ML18018B529 (5) | |
Text
Q iC t
PEC i4 Docket Nos.:
50-400 and 50-401 Mr. Jeremiah Ray Chairman, Advisory Committee on Reactor Safeguards U.
S. Nuclear Regulatory Commission Mashington, D.
C.
20555
Dear Mr. Ray:
DISTRIBUTI Document-vol (50-400/401.)-
NRC PDR L PDR NSIC PRC System JLee Lllheeler BBuckley GMKnighton TMNovak
LB83 Reading
Subject:
Issuance of Safety Evaluation Report (Shearon Harris 1
and 2)
Enclosed for review by the Committee are twenty (20) copies of the Safety Evaluation Report prepared by the Office of Nuclear Reactor Regulation in the matter of the application filed by. Carolina Light and Power Company for licenses to operate Shearon Harris Nuclear Power Plants, Units 1
8 2.
At this time, fourteen issues remain outstanding.
These issues are identi-fied in Section 1.7 of the SER.
Also, TMI-related issues are covered in the SER.
The staff will require the resolution of all open items prior to a decision of issuance of operating licenses.
Sincerely, js Thomas M, Novak, Assistant Director for Licensing Division of Licensing
Enclosure:
Safety Evaluation Report (20) 8312270009 831214 PDR ADOCK 05000400 E
PDR Jl okapi OFFICE/
SURNAMFQ OATEf DL'k
~ ~ ~ 0 ~ 0 ~ 0 ~
BBuc
~ 0/
~ ~ ~ 0 ~ ~ ~I Hey,' t Q /g /83
~ttO ~ 1 ~
~ ~ ~ ~ ~ ~ ~
~.1
~ ~ ~ ~
L.
Gl<
on
/ $/83
~ o(Ve ~ ~
~ ~ ~
L'D ak
~ ~ ~ ~
~ ~ ~ ~ ~ ~ ~
~ ~ I ~ ~ ~ ~I ~
~ ~
~ P'll~ ~ ~ ~
lO ~ ~ 0 ~ ~ ~ ~ ~
NRC FORM 318 t10~) NRCM 0240 OFFlCIAL RECORD COPY USOPO: 1991M35.960
'h
't ~
FRO4J:
ACTIONCONTROL DATFS CONTROL NO.
COMPL DEADLINE A('.RS:
l. Bender TO:
Gossick ACKNOWLEDGMENT INTERIMREPLY FINALREPLY FILE LOCATION DATE OF DOCUMENT 10 PREPARE FOR SIGNATURE OF:
Q CHAIRMAN Q
EXECUTIVE DIRECTOR OTHER:
DESCRIPTION Q LETTER Q MEMO Q REPORT Q OTHER SHARON HARRIS NUCLEAR PLANT, IN(UIRY REGAR RESOLUTION OF ACRS GENERIC ITEMS SPECIAL INSTRUCTIONS OR REMARKS ACRS to transmit to Congressional ING Committees by 10-14.
Notify MaI"go (7585) if there is reason to delay.
PDR - suspense date 10-17-77
'OCUMENT/COPY NO.
NUMBER OF PAGES POSTAL REGISTRY NO.
CLASSIFIED DATA CLASSIFICATION CATEGORY Q
NSI QRD Q FRD Please notify Hugh Vovess, ACRS, when this letter is put in PDR ASSIGNED TO:
Case DATE 10-INFORMATIONROUTING Gossick Volgenau Dircks
~Central Rehm HanaueI Minogue Q
FINAL Q
COPY LEGALREVIEW ASSIGNED TO-NO LEGAL OBJECTIONS NOTIFY:
Q EDO ADMIN&CORRES BR EXT.
COMMENTS, NOT IFY:
EXT.
DATE Q YES Q
NO JCAE NOTIFICATION RECOMMENDED:
NRC FORM 232 (11 75)
EXECUTIVE DIRECTOR FOR OPERATIONS PRINCIPAL CORRESPONDENCE CONTROL DO Ii/OTREilfOI/E THIS COPY
t,i~"<cd t
g('p
~ '~
fp0 Cy
)
I cl O
+>>*++
t'NITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 October ll, 1977 Mr. Lee V. Gossick Executive Director for Operations U. S. Nuclear Regulatory Comnission Washington, DC 20555 SUBJECZ:
SHEARON HARMS NUCLEAR PLANT, INQUIHIl'EGLE)ING RESOLUTION OF ACRS GENERIC ITEMS
Dear Mr. Gossick:
The ACRS has been informed by the NRC Staff that, during the Shearon Harris pre-hearing conference on June 19, 1977, Atomic Safety and Licensing Board Member Dr. J. V. Leeds, Jr. requested guidance from the ACRS regarding which items in the Committee list of Generic Items for Light-Water Reactors must be resolved prior to the issuance of a construction permit, and which must be resolved after construction permit issuance, but prior to issuance of an, operating license.
The Unresolved Generic Items listed by the ACRS have the following characteristics:
a)
They are items of concern to the ACRS for which neither the ultimate solution nor its implementation for reactors in various stages of licensing, construction or operation have yet been determined.
b)
They are applicable not only to a given plant or license application but also to a class of plants or, in som
- cases, to all light~ater reactors.
In the ACRS review of a particular application, it may be decided that certain of the Generic Items should be resolved prior to issuance of a construction permit or, more likely, prior to operation of the plant.
In such cases, a recommendation to this effect is made specifically in the body of the'CRS letter.
Rec'd 0<<
Date (2
7 Z~me
Mr. Lee V. Gossick October ll, 1977 Those Generic Items referred to, and now listed explicitly, in the penultimate paragraph of the ACRS letter, are intended to be considered generically, outside the scope of the particular licensing action.
It is the intent that, when solutions are found, a determination will be made by the HRC Staff and the ACRS as to their implementation on all plants for which they are applicable and necessary.
Sincerely yours, M. Bender Chairman