ML20247D937
| ML20247D937 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/23/1989 |
| From: | Sucheski L ROCHESTER GAS & ELECTRIC CORP. |
| To: | ROCHESTER GAS & ELECTRIC CORP. |
| Shared Package | |
| ML17250A964 | List: |
| References | |
| TASK-03-07.B, TASK-3-7.B, TASK-RR NUDOCS 8909150148 | |
| Download: ML20247D937 (4) | |
Text
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/ ATTACHMENT: A-Rochester Gas and Electric Corporation Inter Office Correspondence p August 23, 1989 l
SUBJECT:
- Structural Upgrade Program !
ATTENDEES: David Jeng - USNRC/NRR Niel Thompson - USNRC/NRR ,
George Wrobel - RG&E Gary Goetz - RG&E Leonard sucheski - RG&E A meeting was held in the offices of the Rochester Gas and Electric Corporation on August 2, 1989 to discuss open issues relative to the Structural Upgrade Program for Ginna Nuclear Power Plant. Specifically, the ninc issues attached to the letter from R. Kober (RG&E) to the USNRC dated May 26, 1987 were discussed.
Of the nine issues discussed, the following required additional
- follow-up by RG&E
NRC Comment 1:
The licensee should assess actual thermal loads for use in load combinations for any areas of the plant known to have high operating temperatures (e.g., concrete surrounding the reactor vessel).
RG&E Response:
This specific subject was reviewed in TER-C5506-423 for SEP Topic III-7.B, prcvided as an attachment to the NRC's SER of August 22, 1983. The worst-case condition was analyzed, and found to be acceptable. Furthermore, during normal operation, there are no
. concrete regions subject to temperatures in excess of 150*F.
Therefore, it is considered that RG&E has already adequately assessed the proper thermal loads for use in the load combin- )
ations.
Attachment 1 is a listing of various thermocouple whose temper- 1 ature outputs are continuously recorded in the control room of Ginna Station. The original design requirements of the Contain- j ment Structures limit the concrete surface temperatures to less than 150*F. The average temperature of the atmosphere in
.89G9150148 890831 PDR ADDCK 05000244 P PDR ,
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Containment is less than 120'F. A potential " hot spot" is at the reactor vessel supports. T/C points #13 through #21 (Attachment
- 1) are thermocouple at the resctor vessel supports. The temper-atures are recorded on monitor RK-28A in the control room. The historical values for these points range from 80*F to 110*F. The l current and historical data is available for review.
i NRC Comment 5:
l In demonstrating the adequacy of roof decks, the licensee should account for buckling, taking into account such factors as un-supported lengths, deck shape, and noting that clastic buckling can occur for long, unsupported lengths.
RG&E Response: '
In the July 13, 1984 letter from R. W. Kober (RG&E) to D. M. j Crutchfield (USNRC) it was stated that local buckling would not occur. However, the subject of deck capacity relative to length was not specifically discussen. The following additional RG&E comments apply relative to this issue.
As defined in the " Cold-Formed Steel Design Manual" of the American Iron and Steel Institute, the metal roof decking used at Ginna is considered a multiple stiffened element. Because of its shape and the width-to-thickness ratios of the compression zones of the deck, the full bending capacity of the shape can be i
developed. In other words, the capacity of this type of section i
is not dependent on length as it is for usual structural members.
Therefore, RG&E*s position is that no local buckling of the roof decking will occur.
The theoretical basis for the discussion of critical buckling of thin plates in compression is treated in the text book " Buckling Strength of Metal Structures" by Freldrich Bleich, McGraw Hill Book Company, Inc., 1952. This book is available for review in RG&E's offices.
NRC Comment 8:
The licensee has committed to evaluate the effects of masonry blockwall failure on main steam and feedwater lines and assoc-1sted valves, and to prevent the walls from entering the spent fuel pool.
RG&E Response:
As noted in RG&E's July 13, 1984 submittal, RG&E has agreed to evaluate the effects of masonry wall f ailure on the main stema and feedwater lines, and associated valves, and the spent fuel pit. The modifications to prevent damage to the required steam and feedwater piping, and associated valves, have been completed in 1988. The modification to prevent damage to the spent fuel due to failure of the block wall on the north side of the spent fuel pool has already been completed. The block wall
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on the west side of the spent fuel pool is not expected to adversely effect the integrity of the fuel in the spent fuel pool, such that the guideline exposures of 10 CFR Part 100 wouldbo exceeded. Calculations indicate that the effect of l
failure of this relatively small wall is bounded by the previously accepted effects of a design basis tornado missile.
Thus, no modifications are expected to be required for this wall.
Attached are calculations which address the issues of main steam and feedwater line integrity from block wall collapse and an analysis of the west block wall of the Auxiliary Building near the spent fuel pit (see Attachments 2, 2A).
NRC Comment 9:
The licensee has committed to assure operability of the power supply and piping associated with one auxiliary feedwater pump, assure sufficient instrumentation to monitor safe shutdown conditions, and to perform an evaluation of the effect of de-pressurization on diesel generator operability.
RG&E Response:
RG&E has completed the rerouting of the auxiliary feedwater system and its controls.
RG&E has completed the majority of the engineering to assure operation and protection of the diesel generators. Physical modifications to accomplish this commitment will be installed and completed by the end of 1990.
The existing diesel generator building is being upgraded to current criteria for all SEP load conditions including seismic.
A copy of the design criteria is attached (Attachment 3).
On the question of diesel operability under differential pressure refer to Attachment 3A which summarizes a conversation between RG&E's Mechanical Engineer and his counterpart at ALCO, Ginna's diesel manufacturer.
Leonard A. Sucheski Structural Engineering LAS:mkv/A070 Attachment xc: G. Goetz G. Wrobel w/ attachment P. Wilkens B. Snow R. Mecredy File
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% . ., ATTACHMENT 1 -
POINT ASSIGIOENT SHEET RK-28A LPOINT'# T/C # SERVICE
.1' 2115 ' STATION SERVICE WATER PUMP'1A 1
.i MOTOR THRUST BEARING 2 2116 STATION SERVICE WATER PUMP 1B MOTOR THRUST BEARING 3- 2117 STATION SERVICE WATER. PUMP 1C MOTOR THRUST BEARING 4' 2118 STATION SERVICE WATER' PUMP 1D' MOTOR THRUST BEARING
.5 2.t o 3 STATION SERVICE WATER PUMP'1A MOTOR UPPER 6 2154 STATION SERVICE WATER PUMP 1B MOTOR UPPER 7 2155 STATION SERVICE WATER. PUMP 1C MOTOR UPPER 8' 2156 STATION SERVICE WATER PUMP ID MOTOR UPPER 9 2135 AUX.'M.D. FEEDPUMP 1A INBOARD MOTOR l .10' 2136 AUX. M.D. FEEDPUMP 1A'-
OUTBOARD MOTOR 11 2137 AUX. M.D. FEEDPUMP 1B INBOARD MOTOR 12 2138 AUX. M.D..FEEDPUMP 1B
, . OUTBOARD MOTOR 13 2175 SUPPORT PAD lA ----- 80'F 14 .2177 SUPPORT PAD 1B 15 2179 SUPPORT PA3 1C 16 2181 SUPPORT PAD 1D 17 2183 SUPPORT PAD 1E 18 2185 SUPPORT PAD 1F 19 2187 SUPPORT PAD 1A 2 0 __ '2189 SUPPORT PAD 1C 21 2191 SUPPORT PAD IE- ----- 110*F 22 2167-EAST ANNULUS AIR TEMPERATURE 23 2168-SOUTH ANNULUS AIR TEMPERATURE 24 2169-WEST ANNULUS AIR TEMPERATURE 25 2170-NORTH ANNULUS AIR TEMPERATURE 26 2171 LOOP "A" HOT LEG REACTOR NOZZLE EXHAUST AIR 27 2172 LOOP "A" HOT LEG REACTOR NOZZLE EXHAUST AIR 28 2173 LOOP "A" HOT LEG REACTOR NOZZLE EXHAUST AIR i
1 l