ML20082H590
| ML20082H590 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/04/1995 |
| From: | Penland T TROUTMANSANDERS (FORMERLY TROUTMAN, SANDERS, LOCKERMA |
| To: | Carpenter J, Murphy T Atomic Safety and Licensing Board Panel |
| References | |
| CON-#295-16594 OLA-3, NUDOCS 9504170243 | |
| Download: ML20082H590 (7) | |
Text
___ _
'/lp59f v
TROUTMAN SANDEdR
.. u.a.m. w. a... u......,%y NATN3NSGANK PLAJA 600 PEACHTHEE STREET.N E RutTE 5200 ATLANTA. GEORGIA 307 4 2216 95 Nn -6 P3 :12 TELEPHONE 404 8FS-3000 FACSIMILE 404 6# $ 3900 DmECT 404 885 3471 THOMAS L PENLANQ JR April 4,1995
([
Peter B. Bloch, Administrative Judge Atomic Safety and Licensing Board Thomas D. Murphy, Administrative Judge Atomic Safety and Licensing Board James H. Carpenter, Administrative Judge Atomic Safety and Licensing Board Re:
Georgia Power Company (Vogtle Electric Generating Plant, Units I and 2) NRC Docket Nos. 50-424-OLA-3, 50-425-OLA-3; License Amendment for Transfer to Southern Nuclear Operating Company
Dear Board Members:
The purpose of this letter is to forward a corrected exhibit for Georgia Power's prefiled testimony of Mr. Georgie R. Frederick, submitted April 3,1995, and to supplement a prior response to Licensing Board questions. Mr. Frederick's prefiled statement, Exhibit B (Georgia Power Exhibit 47) should consist oflunc 8,1990 Plant Review Board Minutes, rather than the May 8,1990 Plant Review Board Minutes forwarded on April 3rd. A copy of the correct Exhibit 47 is enclosed.
On July 20,1994, Georgia Power Company's Response to the Board's June 9,1994 Memorandum and Order (Board Questions and Concerns) included an Affidavit of Mr. Lewis Ward as Exhibit 3. Page 4 of Mr. Ward's Affidavit appears to have been omitted in the filing; a copy of page 4 is included in Mr. Ward's prefiled testimony (Georgia Power Exhibit 63).
Copies of Georgia Power's Exhibit 47 are being provided to the parties by means of this letter.
Very truly yours, ff Thomas L. Penland, Jr.
l TLP:ss
Enclosures:
as Stated cc:
Service List 9504170243 950404 3
PDR ADOCK 05000424 yp0 o
PDe
.1
FREDERICK EX. B
... ~.
j VEOP PLANT REVIEW BOARD MEETING MINUTES i
J j
uzRTINo No.
so-si DATs e/8/so PAGE 1
or s
t
{
.EETING CONVENED 1810 AN/PM; MEETING ADJOURNED 2: 40 AN/PM j
(
- VIA TELECON)
THIS NzETING CHAIRED BY3 j
() CHAIRMAN (X) VICE CHAIRMAN T. V. Greene i
1 VOTING NENBERS PRESENT3.
N. M. Handfinger J. G. Aufdenkampe
]
i PRB SECRETARY C. Cross Tynan 1
l NON-VOTING MEMBERS PRESENT:
G. R. Frederick C. P. Stinespring
)
J. B. Beasley i
VOTING ALTERNATES PRESENT:
J. P. Cash FOR J. E. Swartzvelder i
l R. L. Mansfield FOR M. W. Norton NON-VOTING ALTERNATES PRESENT:
l P. A. cure FOR R. L. IAGrand FOR l
F.OR j
FOR l
GUESTS /T::CHNICAL ADVISORS:
l T. E. Webb G. S. Lee i
1 PRS ACTION ITEMS OPENED:
None 4
PRB ACTION ITEMS CIASED:
PR5-90-66-01 PRS MINUTES APPROVED s'
90-76, 90-77, 90-78, 90-79, 90-80 1
& k. ha bnA
\\pt % A, Q i
593 SECRETARY PRS CHAIRNAN 4
I CC: NRC RESIDENT INSPECTOR I W W W188'=cen
'Um t.
~ -.
I l
1 4
i 1
PR5 90-81 Page 2 of 5
\\
o l
PRS MEETING MINUTES CoarFINORTION 8535T t
I' i
j A.
Meeting Minutes 90-76, 90-77, 90-78, 90-79 and 90-80 were j
unanimously approved as presented.
I a.
The f9J1owing items were unanimously recommended for j
approval.
No unreviewed safety question involved.
j TCP 12309-1-5-90-1
" Gaseous Releasee 8L TCP 18019-C-7-90-3 "losa of Residual Heat Removal #
l TCP 18038-1-10-90-2
" Operation Frous Remote j
shutdown Panels' TCP 18038-2-5-90-2
" Operation Prost Remota a.
Shutdown Panels" l
TCP 19241-C-7-90-2 "FR-P.1 Response To Imminent Pressurised Thermal shock condition" j
TCP 19232-C-3-90-2 "FR-H.2 Response to steam l
Generator overpressure"
{
19232-C, Rev. 4 "FR-H.2 Response to steam Generator overpressure" TCP 83503-1-1-90-1
" Unit Operation During l
Secondary Plant l
Performance Test" 1
83503-1, Rev. 2
" Unit Operation During seMery Plant l
Performance Test" I
Special Report 1-90-04
" Valid Diesel Generator
~
j Failure" (NOTS-00403) l DCP 90-V1N0015, Rev. O To eliminate.the possibility of the ARV's stalling at some uncontrolled position after several strokes TER 90-004, Rev. 0
" Turbine-Generator Torsional Test" (Results).
IsI-P-014, Rev. 3
- i.
PRB 90-81 j
Page 3 of 5 l
LER 2-90-01, Rev. 1
" Misleading Task Sheet Leads to Inadequate 1
)
Technical specification l
Surveillances".
t i
c.
The following items were unanimously recommanded for approval with comment.
No unreviewed safety question l
involved.
0
$3020-C, Rev. 5
" Technical Inspection'of New Fuel".
Section 3.0 -
j should include precaution on use of HP requirements /NNP.
Step 4.1.14 - should Rad.
1 l
Naterials shipping Form j
and/or DDR 741 Form be included here?
j DCP 90-V130157, Rev. 0 To reduce nuisance tripping of the Diesel Generator Fuel 011 Transfer _ Pumps on thermal i
overload and stop leakage i
of fuel oil around pump base.
should specify functional test requirements via Data l
sheet 12.
Question 2 mil packing reduction appropriateness when i
problem may be corrected j
by installing vertical i
pump.- Revise / markup i
transmittal letter to i
correctly reflect package
{
and return.
i
~
j D.
The board unanimously concurred with the reportability j-determination for the following Defici'ency cards.
1-89-1579 1-90-260 l
1-90-261 1-90-262 j
1-90-264 I
4 3
i I
i
1
!~
l~
PRS 90-81 j
Page 4 of 5 l
E.
The board tabled procedure 00643-C, Rev. O, " Fitness-For-Duty", with the following comment.
Step 4.1.3 - Change to Vogtle - Southern company section 3.0 - Responsibilities of individuale and/or i
j groups offaite (not reporting to GMNF) should be put in another part of procedure as Appendix or such.
i step 3.7 - Change "at each plant site' to "at Plant volgtle" Confidentiality compromised for self referrals (since va approves return to work) j Will grieving employees be paid?
j section 8.3 - currenti escorts are not trained in Aberrant Behavior - on y supervisors get aberrant behavior training.
Alcohol (positive) testing doesn't require VP approval i
for return to work (self referral yga, for cause).
i I
F.
The board tabled TCP~18028-C-7-90-1, "Imes of' Instrument i
Air".
Operations will review th$ TCP to determine if the TCP is valid or should be voided.
The board expressed a i
concern relative to the proposed deletions.
4 G.
PR5 Action Item 90-66-01 was reviewed.
W. F. Kitchens responded to a request by the PR8 that the Trip Reduction committee re-evaluate Trip Hasards~ Labeling.
This resulted from the boards' review of LER 1-90-011.
The response stated that the Trip Reduction Committee has initiated a review of labeling / signs for critical components.
The Trip Reduction Committee is not re-evaluating Single point trips, and does not intend to at this time.
Se Committee is looking at several specific trip reduction issues.
It was stated that last year, the Trip Reduction Countittee reviewed i
and concurred with an Engineering support r- - ndation to i
stop spending resources on the Single point trip studies, l
but rather on specific trip reduction measure.
4 i
Based on this response PR5 Action Item 90-66-01 was closed.
i l
H.
The~ board reviewed a letter from the General Manager -
Nuclear Plant to' FR5" and WR1r feast $str Win.nning' tile reportability review of Deficiency Card 1-90-003, and the boards' split decision that the item was not reportable.
l This deficiency involved a potential violation of a license j
condition, specifically the reactor power limit of 3411 Mw.
The lotter states that based on additional reviews that were 3
j completed, it was verified that the iten was not reportable.
The board concurred with this position, and the letter is being made an attachment to the minutes for this FRE Meeting.
+
4 g..
.,,,...,,,y.,
PRS 90 '
P gn 5 of 5 I.
Revision 1 to LER 1-90-06 (site Area. usergenoy) was returned to the board from corporate with comments as to why the revision was warranted and requested revised wording on the diesel start section.
The LER revision 1 was previously reviewed and approved by the PRB on May 8, 1990 and forwarded to corporate at that time.
The board decided to table the proposed LER revision presented so that the entire LER could be updated and returned to the PRS et a future meeting.
G. R. Frederick added that he felt the diesel start numbers in the original LER were incorrectly included because of various probless/ confusion with the surveillance and operator logs and-the trending information recorded by Engineering support.
I J.
J. G. Aufdenhampe addressed the board on a previous reportability issue for a proposed LER involving a potentially missed surveillance on containment Penetrations.
The PRB concurred that the Dc was.not reportable at PRB-90-76.
J. G. Aufdenkampe stated that he had spoken with the NRC Residents and that they had concurred with the PRB's decision after they were provided with the information from Outage and Planning (which the,PR3 utilised in making the reportability determination).
J.
G. Aufdenkampe informed the board that the Vice President, C. R. Necey stated that the ites should not be reported because of the installed blind flanges but he felt that an inadvertent compliance issue may preside in this issue.
J. 4. Aufdenkamps took the action to discuss this item with the General Manager and would report back to-the board only if a change in j
reportability would be appropriate and the proposed LER was required to be submitted by corporate.
i Meeting Adjourned i
i i
a d
4 m e
-.n-,
,.e.,
...-n,
i GeorgiaPower A I'
interofilce Correspondence i
i I
l CME:
June 4, 1990 RE:
Reportability Determination for Deficicacy Card 1-90 003 Tog: NOT3-00383
)
FRON:
G. Beckheid, Jr.
70:
PA8 Members and $A8 Members On January 5.1990, the PR8 met to review the reportability of ceficiency Card 1-90-003. This deficiency involved a potential l
violation of a licence condition, specifically the reactor power limit of -3all MW The board determined in a split decision that the item wasnotre$r. table.
Subsequently, I requested thet more information be obtained during additional reviews to verify that the ites was not reporta61e.
i Mr. J. G. Aufdenkampe, on January 10, 1990, issued a minority i.
opinion questioning the recommendation of the PRS. My decision not to report this item on Janury 5,1990, was besed upon the esjority recomendation and my belief' that more information would be expeditiously provided by Mr. Aufdenkampe and his Technical Support j
Department.
The additional reviews were completed and verified that the item was not reportable. If you have any questions.or require additional i
information, please let me know.
b I
xe: NOM 6 4
4 n
4
-v n
w
-c
,e,u m
w a
,-,-w w em oe--a