ML20247L868
| ML20247L868 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/25/1989 |
| From: | Hayes J Office of Nuclear Reactor Regulation |
| To: | Cantrell F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| TASK-1.C.1, TASK-1.D.2, TASK-2.D.1, TASK-2.K.3.01, TASK-2.K.3.05, TASK-TM NUDOCS 8906020284 | |
| Download: ML20247L868 (2) | |
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UNITED STATES '
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May 25, 1989_
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1 MEMORANDUM F.0R:;
- Floyd S. Cantrell Chief, Section I-B.'
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Division of Reactor Projects 1
Region II FROM:..
John J. Hayes, Jr.
Project Manager, V. C. Sumer Project Directorate 11-1
. Division of Reactor Projects 0ffice of. Nuclear Reactor Regulation
SUBJECT:
STATUS OF TMI ITEMS-FOR THE V. C. SUMMER NUCLEAR STATION, UNIT NO.=1 a
You' requested documenting' of our telephone. conversation of April 6, 1989 on the status.of.the outstanding TMI items which were listed in the Region II's report on the V. C. Summer Nuclear Station dated March 15, 1989.
The status of.theLTMI items from the Region's report is shown as Attachment 1.
Items I.C.1.2.B and I.C.I.3~.B, Core Cooling and Transients, respectively, will
-comments'on_theSummerProcedure'GenerationPackages(PGPs)plantspecific be addressed in an SE' issued by NRR. This SE will provide The licensee
- is to incorporate the comments and if they decide not to incorporate the coments, then they must maintain a copy of the justification as to why the-s coments were not incorporated.- The Summer SE is anticipated to be. issued '
.during the sumer of 1989.
iAs" discussed with.you on April 6, Items I.D.2.2 and I.D.2.3, SPDS Installed and-SPDS1 Implemented,..respectively, will be completed during, the next refueling outage presently scheduled for April-June:1990. You should note 'that Summer currently has received from the NRC.a'SE on their presently installed SPDS system. The SE indicated that'the installed SPDS was' adequate to operate;
- however, there'were a couple of open items associated with the SPDS. The licensee, rather than address the open items, decided to modify the hardware I
and software' associated with the SPDS.
NRR will review the proposed modification at information becomes available.
Items II.K.3.1.B and II.K.3.5.B. Auto PORV Isolation and Auto Trip of RCPs, respectively, indicate that the status / action is that both items are awaiting an-implementation audit. My discussion with the PM associated with II.K.3.5.8 indicates that no implementation audit is planned for this item. My t
discussion with the technical reviewer from NRR responsible for this item indicates that no TI is being prepared.
It can be assumed that the same is true for'II.K.3.1.B since this item was implemented several years ago at most facilities and a TI has not been prepared and an implementation audit has not occurred. Therefore, closeout of this through verification does not appear iminent.
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[lYour:listofTMIlitemsismissingII.D.1,RVandSVTesting..The' licensee owes.the NRC a response.' They anticipate making their. response by June.1, Original Signed By:
' John J;. Hayes, Project Manager Project Directorate II-1 Division of Reactor Projects -I/II Office of Nuclear Regulation cc:
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