ML17256A412
| ML17256A412 | |
| Person / Time | |
|---|---|
| Site: | Ginna |
| Issue date: | 12/02/1982 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.2, TASK-2.B.3, TASK-2.D.1, TASK-3.D.3.4, TASK-TM NUDOCS 8212080384 | |
| Download: ML17256A412 (8) | |
Text
REGULATORY I RMATION DISTRIBUTION "SYS I (RIDS)
ACCESSION NBR 821208038 f
DOC ~ DATE 82/12/02 NOTARIZED NO DOCKET FACIL:50 244 Robert Emmet Ginna Nuclear Plantg Uni't lr Rochester G
0500024Ll AUTH,NAME AUTHOR AFFILIATION MAIERiJ ~ Ee Rochester Gas
- 8. Electric Corp>
REC IP, NA~<E RECIPIENT AFFILIATION CRUTCHF IELDiD ~
Operating Reactors Branch 5
SUBJECT:
Advises of expected completion dates for TMI Items II,BE 2 re radwaste remote control sysiII,B,3 re post accident sampling sys< II>D. 1 re safety 8, relief valve testing 8 III'E 3.0 re control room HVAC mods, DISTRIBUTION CODE:
A006S COPIES RECEIYED:LTR ENCL /
SIZE:
TITLE; OR Submi,ttal:
TMI Action Plan Rgmt NUREG 0737 8
NUREG-0660 NOTES:NRR/DL/SEP
- 1cy, 05000244 RECIPIENT ID CODE/NAME NRR ORBS BC '1 INTERNAL: ELD/HOSE IE/DEP EPDS NRR/DHFS/DEPY29 NRR/DL/ADL 16 NRR/DL/ADSA 17 NRR/DS I/ADRP 26 NRR/DSI/AE8 NRR/DS T DIR'0 RGN1
'XTERNALo ACRS 3Q INPOgJ
~ STARNES NRC PDR 02 NTIS I NOTES:
COPIES LTTR ENCL 7
7 1
0 1
1 1
1 1
1 1
1 1
1 1
1 1
1 10 10 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME IE/DEP D IR 33 IE/DEP/EPLB NRR/DL D IR 14 NRR/DL/ADOR 15 NRR/DL/ORAB 18 NRR/DS I/ADRS 27 NRR/DSI/RAB L
00 FEMA REP DI Y LPDR 03 NSIC 05 COPIES LTTR ENCL 1
1 3
3 1
1 1
1 3
1 1
1 1
1 1
- -1 1
1 TOTAl NUMBER OF COPIES REQUIRED; LTTR 45 ENCL
Hxh Hhsgf h
4
)II I!4<<
7 4
x th (,l(h H
4h qHh!p l(
H III (
)kh 'H i( li H h
~ ) " )
h
'li' f H,II, I ~
I 4X ll
'(II Ilk 'i
'k i, > '
k I,H P, 4 'I
"'I 4
4 0 H
~
hl qJ I 'lps g I,)l I 'h [ sh!'),H)>>,
(hf lay 4 S
, ~
hX a
J')
Ilf HI
,I J ) ] ll
')x
'h 4> H1 j) ~,s
'P wq 4
h f fs H'Hf )HX,,) li h(l g(HHP e
J h y ~g H
) t4
~ g'('(hH(4)
(H,) ~ ~
LP Hl j 4
g g
l (k,s
I 4
lp
)( H y " 'I ~
(4 tI g
g H
)
P "h H \\ HWf
'p 4) 1'hH I
'1 ii
)
h il, p CH!,f
i hg h
h I
(Ill(i 4(l
~ lt )
X g I hhs "h Ilil ~ FH i
!IJE'(
If 4 '(
a'Hs)
)
()
HX4h ih H'
I
',id 41 Il h'J
'h'a 4I X
)
< 'x )x h
H, 4(
( s(
H H'H
~
i f I) jx I
(.4
'( l g
g 4
Hs i
4 4
Hh Xr,.
Ib illi) 4 X IH(1 o. II)").H N
II h
s h
H ',
H, ll
)
II/If)IF)($
I!/Il LLal 0 ~ Isa IIIIII /I
/i/IIIIIIII ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 5TATE J055N Ei MAILER Vioo Prooldont T CLKP H0 N 5!
- oci cooc>>e 546-2700 December 2,
1982 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Post-TMI Requirements R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
The purpose of this letter is to inform you of the expected completion dates for four post-TMI requirements:
a new radwaste remote control system under NUREG-0737 item II.B.2, a post-accident sampling system (PASS) under item II.B.3, safety and relief valve testing for item II.D.l, and control room HVAC modifications under item III.D.3.4.
Letters dated December 15,
- 1980, September 4,
1981 and November 25, 1981 have described the radwaste remote control system modifica-tion and its installation schedule.
Our shielding and dose studies following the TMI accident indicated that it is prudent to have the capability to operate portions of the existing radwaste equipment from a remote location even though experience at TMI has shown that existing equipment configuration will probably not be used for long-term recovery and cleanup following accidents with similar fuel damage.
Existing radwaste equipment may be used following less significant accidents.
Because it is difficult to define when the radwaste equipment.
may be used and because the modification will aid in our normal operation ALARA program, we have committed to installa-tion of a new radwaste remote control system.
Our previously scheduled installation date was November 1982 based upon equipment delivery-in September and a preliminary, construction estimate of two months.. All of the equipment has, not'yet arrived on site but it is expected by mid-December.
Finalization of the design has shown installation will require significantly more construction work.
Ne now anticipate a work start. authorization in early January 1983.
Construction will take "approximately four months and thus will be completed in May 1983.
Testing to confirm operability of the remote control system will follow installation.
This is the first 8212080384 821202 PDR ADOCK 05000244
'I P
f VV I
~-
t, I'>>
l,l
'I
4 I VI 4
+VV = gWQ'YV>
4 4,
~ 4
~
- Sf)
ROCHESTER GAS AND EL TRIC CORP.
DATE December 2,
1982 TO Mr. Dennis M. Crutchfield SHEET NO 2
computer-based digital controller to be used at Ginna so that the amount of system testing and trouble shooting that will be required is unknown.
Experience with other types of recently installed equipment leads us to estimate that system debugging will probably take 60 to 90 days following installation.
Thus we expect to have the radwaste remote control system operable in July 1983 unless unforeseen difficulties arise.
The PASS schedule is unchanged since our reevaluation following a contractor-employed labor personnel strike.
We are nearing completion of the PASS installation.
Concurrent with construction, preoperational testing of the system is being performed,.
During this testing a valve in.the 'discharge line of the PASS to ~the containment sum'p has'ailed.
Since this valve 'is inside the
'ontainment vessel, it cannot be replaced until our March 1983 shutdown.
j I
The valve is not necessary to obtain the"samples required by NUREG-0737 but it does affect the disposal of samples.
Samples drawn using the PASS must be directed to the waste disposal system or isolated in shielded containers.
Unless other failures which cannot be corrected without an outage occur, the PASS will be operational by mid-February
- 1983, as stated in our letter of September 16, 1982.
The option to discharge samples to the contain-ment sump will not be available, however, until the failed valve can be replaced.
The safety and relief valve testing item, II.D.l, has yielded preliminary results that show that the Ginna pressurizer safety and relief valves will function in an acceptable fashion.
Two evaluations remain to be submitted.
The first is to verify our preliminary evaluation that the specific valves used at Ginna will function adequately under all expected operating conditions.
The second is to confirm the adequacy of safety and relief valve piping.
We anticipate having all analyses complete and a final report prepared by February 1983.
To date no modifications have been identified which are required to ensure the operability or integrity of the relief and safety valve system.
A few minor modifications will be made to the supports for relief piping lead-ing to the pressurizer relief tank (e.g.
support shims),
- however, these modifications are not required for the relief and safety valves to function properly.
The modifications will be made to ensure that analysis assumptions are valid for downstream piping, although not required for valve operability, and to assure that fluid relieved from the pressurizer will be directed to the relief tank.
No modifications are anticipated to comply with TMI Lessons Learned requirements.
Submittal of the final reports should complete the action items.
e II
~
~'
C I
1
/
C C 'I C
C ~
I Pry C
< 4 lI
)
ggyC) ir C)
I)
I IfI C I'"(I I
I il ~
~
~
~ 't I
I I
C C
I WPC ~')
C
$ ~
'f I
C III wigr)
~
qy )
)
C
<) I' I'
C I'
~'OCHESTER GAS AND EL RIC CORP DATE December 2,
1982 TO Mr. Dennis M. Crutchfield
)SHEET NO.
3 Letters dated September 4,
1981 and June ll, 1982 identified modifications planned to comply with item III.D.3.4, control room habitability.
The modifications included adding detectors for ammonia, chlorine and radiation in the air intake to automatically isolate the HVAC system.
We also committed to evaluate charcoal filter residence times and to evaluate alternatives for reducing control room ammonia concentrations.
We have concluded that the ammonia tank should be relocated to reduce the risk of elevated ammonia concentrations in the control room and have prepared a pre-liminary design.
, We anticipate beginning the relocation during the summer of 1983.
The other modifications and the charcoal filter residence time evaluation have been delayed to consider the impact, of SEP and environmental qualification reviews upon the control room HVAC system.
We also acknowledge receipt of your October 18, 1982 letter requesting modifications to-the intake and exhaust ductwork to install additional dampers.
It is best to coordinate all of the reviews and design changes in a single modification package.
Nevertheless, it, appears that, the addition of detectors for toxic substances can be installed without significant impact on the remainder of the system.
If this is the case, these modifica-tions can be installed during the 1984 refueling outage.
Lead times for the equipment extend beyond the 1983 refueling outage.
An outage is required for installation because of syst: em operability requirements during operation.
The added detectors and the relocation of the ammonia tank will complete the modifications to limit toxic substances in the control room by the end of the 1984 refueling outage.
Any additional modifications resulting from SEP review, environmental qualification, or your recent letter are anticipated to be performed on a schedule consistent with the currently proposed regulation 10 CPR 50.49.
Very truly yours, Jo n E. Maier
4 pf Pll
+ SV
~
eh I'
,r, ~ ~
~
~" a-r I II WC