ML19329B203
| ML19329B203 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/29/1977 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19329B196 | List: |
| References | |
| NUDOCS 8001310554 | |
| Download: ML19329B203 (2) | |
Text
O.
O APPLICATION FOR AMENDMENT TO LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Enclosed are forty-three (4ai copies of the requested changes to the Davis-Besse Nuclear Power Station Unit 1 Technical Specifications, Appendix A to License.lo. NPF-3 together with the reasons for the change and the safety evaluation of the requested change.
d By b Vice President, Facilities Development Sworn to and subscribed before me this 29th day of July, 1977.
Y
he M
~
Notary Public FRED W. GERMAIN Mctary Public. Lucas. Wocd Henry.
Fulten & Ottawa Counties. Ohio My Commission Expires Oct.30.1977 8001310
.s.
DB-1 REQUESTED CHANGE TO THE DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 TECHNICAL SPECIFICATIONS (App. A to Licer.se No. NPF-3) j Table 4.3-1, Reacter Protection System Instrumentation Surveillance Requirements, should be revised as shown on the next page to reduce the Channel Calibration Surveillance Frequencies for Functional Units 5, 6 and 7 from once every 120 days to once every 18 months (denoted by the letter R).
4 l
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TABLE 4.3-1 y
REACTOR PROTECTION SYSTEM INSTRul1ENTATION SURVEILLANCE REQUIREMENTS Y
E CilANNEL MODES IN WHICH E
CilANNEL CilANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CllECK CALIBRATION TEST REQUIRED 1.
Manual Reactor Trip N.A.
N.A.
S/U(1)
N.A.
2.
liigh Flux S
D(2), and Q(7)
M 1, 2
~
3.
RC liigh Temperature S
R M
1, 2 4.
Flux - AFlux - Flow S(4) 11(3) and Q(7,8)
M 1, 2 5.
RC Low Pressure S
R 11 1, 2
",i, 6.
RC liigh Pressure S
R tt 1, 2 I
7.
RC Pressure-Teinperature S
R H
1, 2 8.
liigh Flux / Number of Reactor
{
Coolant Pumps On S
R H
1, 2
<g 9.
Containment liigh Pressure S
R H
1, 2 10.
In tennedi, o Range, Neutron Flux and Rate S
R(7)
S/U(5) 1, 2 and*
- 11. Source Range, fleutron Flux and Rate S
R(7)
!* and S/U(1)(5) 2, 3, 4 and 5
- 12. Control Rod Drive Trip Breakers N.A.
ft. A.
M and S/U(1) 1, 2 and*
j
)
13..
Reactor Trip Module Logic II. A.
fl. A.
M 1, 2 and*
- 14. Shutdown Bypass liigh Pressure S
R M
2**,3'*,4**,5**
.-m
DB-1 SAFETY EVALUATION Revision 25 to the Davis-Besse Nuclear Power Station Unic No. 1 FSAR included the changes to the FSAR reflecting the replacement of the narrow range reactor coolant pressure transnitters with the Rosemont 1152 trans=itters. Page 3-178 addresses the seismic qualification of the Rosecont transmitters and page 3-181 addresses the environmental qualifications of the Rose =ont transsitters. Since these changes are already included in th-F9AR, no further FSAR revisions are required.
The Motorola transmitters which have been replaced had excessive drif t which required a recalibration once every 120 days. The Rosecont transrJ.tters which are installed have much less drifc and do not re-quire recalibration more frequent than once every 18 conths to meet i
the guidelines of IEEE 279-1971.
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