ML20126E175
| ML20126E175 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/27/1973 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8101120451 | |
| Download: ML20126E175 (4) | |
Text
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Disfribution DLZiemann, L:0RB#2 eticket File JJShea, L:0RB#2 AEC PDR g g7 g RMDiggs, L:0RB#2 RP Reading NDube, L:0PS-Branch Reading MJinks, DRA (4)
JRBuchanan, ORNL l)ockat No. 50-155 SKari, L:RP TWLaughlin, DTIE EPA (3)
VMoore, L:BWR DJSkovholt, L:0R TJCarter, L:0R Consumers Power company ACRS (16)
ATTE: Mr. Ralph B. Sewell RO (3)
Nuclear Licensing Maipiatrator JScinto, OGC 212 West Michigan Avenue RVo11mer, L:QA Jackson, Michigan 49201 Change Eo. 38 Licensa 30. DPE-6 g,gy,,,,
We have completed our evaluation of your request dated June 15, 1973, to change the Technical Specifications of Facility License Mo. DPR-6 to:
1.
eliminate tests on the main steam drain (MD-7065) as long as the valve remains closed [Section 3.7(b)],
2.
aliminate coolant recirculation line butterfly valve trip testing requirements because the two valves (one in each loop) are no longer requf: red and have been disablai in the open position
[ Sections 4.1.2(a) and 6.1.2],
3.
require a second AEC licensed operator to confirm that all control rod vithdrawal procedures are followed while control rods are being withdrawn to approach criticality (Section 7.1.2), and 4.
remove reference to the initial Big Rock reactor startg that occurred more than ten years ago (Section 7.2.1).
We have concluded that the technical specification changes you have proposed, as modified to reflect telephons conversations on June 25 and June 26, 1973, with your representative, are acceptable for the reasons you have stated. However, we note that documented analysis (CPCo Proposed Change 13 dated May 26, 1967) of maximum control rod worth and reactivity accidents, relative to the AEC requirement for a second licensed operator during reactor startup to assure adherenca to approved written control rod withdrawal procedures (item 3 above),
apply to Big Rock Point Type C fuel assemblies. According ta the 1967 analysia, the mart== reactivity addition for an in-sequence r
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1-JUL 2 71973 Consumers Power Company i
control rod, if that control rod hangs up and drops to the drive position at the worst time, is 0.008 delta k/h. The mad== reactivity addition for a rod drop accident- (RDA) with a single operator error is 0.021 delta h/k. The calculated results for a 0.021 delta k/k RDA reactivity insertion show that the peak energy density in the fuel is approximately 340'cals/ gram. However, our previous calculations show that with peak energy release. of this magnitude the primary coolant system and core viu not be damaged to the estent that core cooling is ispaired and is therefore acceptable. Further, with no operator error, the==M-=
reactivity insertion is 0.008 delta k/k and the peak energy release would be significantly below 340 cals/ gram, probably below the value currently being accepted by the AEC, i.e.,
280 cals/ gram without performing a prompt coolant energy deposition evaluation.
Since it is planned that reload fual assemblies for the Big Rock Point core beginning with the core refueling in the spring of 1974 will utilise an u a 11 fuel rod lattice instead of the Type C fuel assembly 9 x 9 lattice, you are requested to reassess and quantify, using current analytical methods, the rod drop accident safety margins prior to the next Big Rock Point core refueling.
We have concluded that the technical specification changes, as described i
below, do not present significant hazards considerations and that there is reasonable assurance that the health and safety of the publie vill not be endangered by operation in the proposed mannar. Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, the Technical Specifications of Facility License No. DPR-6 are hereby changed as indicated below 1.
Change Section 3.7(b) to read as follows:
l (b) At least once every twelve months, the following valves shan be tested for operability from both the manual and I
i automatic modes of operation and, at the same time, shan be tested for leak tightnaas by manna of a pressure test j
l utilising air or the normal working fluid at a pressure not less than 20 psig Main Steam Isolation (No-7050)
- Main Steam Drain (No-7065)
Cleanup System Resia Sluice (CV-4091, CV-4092, CV-4093)
Reactor and Fuel Fit Drain Isolation (CV-4027, CV-4117)
I l
Reactor Enclosure Clean Sump Isolation (CV-4031, CV-4102)
Rasetor Enclosure Dirty Sump Isolation (CV-4025, CV-4103) t e a se e g v,w m.,., w,- m ww a
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9 Constamers Power Company JUL 2 71973 All significant leaks (drops /second) revealed by these tests shall require repair of valve seals and ratests.
Automatia controls and instrumentation associated with these valves shall be tested at approximately quarterly intervals; these testa may be conducted with a simulated signal or in such other mannar as to obviate plant shutdown.
- 0perability, automatie sentrols, and instrumentation tests required only if valve is opened for use during operation.
2.
Change summary titled " Recirculating Valves, Each Isop" listed in Section 4.1.2(a) to eliminate the asterick footnote and read as follows:
Mode of Size -
Opening Rate Inestion Type Operation Inches _
Inches / Min Pump Suction Gate Motor 24 12 Ptsap Discharge Cata Motor 20 5
Pump Discharge Cate Motor 5
12 Bypass Valve Pump Discharge Butterfly Electrically Disabled and Locked in the Full Open
(
Position I
3.
Change Item 6.1.2 concerning recirculation line valve closure sensor and trip devices in the " Scram Setting and Tolerance" l
column to raad as follows:
l Approximately 10 percent of full simultaneous closure of j
both discharge or both suction valves or any combination i
of both of these valves, one in each loop.
i 4.
Change Section 7.1.2 to read as follows:
7.1.2 There shall be at least two operations personnel (one of whom shall be an AEC licensed operator) in the control room for startup and shutdown of the plant. A second 4
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6 JUL 2 71973 Consumers Power Company AEC licensed operator shall observe all controZ rod move-monts associated with critical approaches on starty to ensure these control rod movements are performed in accordance with established control rod withdrawal pro-cedures. There shall be at lesst one AEC licensed operator in the control room at other times during power operation and also durfag refueling. No licensed operator shall be required in the control room when reactor is la the cold shutdown condition as defined in Section 1.2.6.
The min 4=um shift complement shall consist of a shif t swervisor and two operations personnel.
5.
Change paragraph (a) of Goetion 7.2.1 in its entirety to read as follows:
(a) Written procedures for normal and emergency operations which may involve nuclear safety shall be prepared, reviewed, and approved by responsible persons designated by the Plant i
Superintendant prior to use. These procedures shall be reviewed at least every two years for any necessary changes s
and shall conform to the Technical Specifications.
Copies of the Site Emergency Plan will be kept in the Control Room, Auxiliary Equipment Room, Information Center, and the Company's General Office.
Sincerely.
Origi.nal Signed by
,D. J. Skovbolt g
Donald J. Skovholt Assistant Director for
~
Operating Reactors Directorate of Licensing
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ces Mr. Paul A. Perry, Secretary
(
Consusars Power Company i
212 Epsf' Michigan Avenue Jac_ hon, Michigan 49201 k
I Kr. Donald W. Aldrich
,i Consumers Power Company
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Legal Department
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212 West Michigan Avenue Jae h _, Kiehigaa 49201
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