ML19329B670
| ML19329B670 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 02/10/1977 |
| From: | Szuklewicz A Office of Nuclear Reactor Regulation |
| To: | Mcgough J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19329B671 | List: |
| References | |
| NUDOCS 8002050778 | |
| Download: ML19329B670 (5) | |
Text
/
0{9T'O
~
\\
o 1
6S TF 0T3 5
2,
- 1] u l_w _a u
l v
, $llU b
fDORANTGI FOR:
J. McCour,h, Group Leader STS Group, D)R FTaf:
A. Szuhiewicz Instrumentation and Control Systems Branch, DSS DIRU:
C. !! iller, Section Leader Instruaentation and Control Systems Branch, DSS
SUBJECT:
DAVIS EESSE INIT 1 UICNICAL SPECIFICATIG;S SECTION 3/4.3 PAGES 9 DIRCCGI 49 In response to your memorandun to T. A. Ippolito dated Jr.nuary 12, 1977, requesting ICSB review of the above sections of the Davis Besse Unit 1 Technical Specificaticns, we are enclosing our ccrrents (see Enclosure A) for ycur consideratien and incorporation into the final teci:nical sycifi-cation doctrent.
A. Szukiewicz Instnrentation and Control Systens T> ranch, DSS
Enclosure:
DISTRIBUTION As stated
.__ Central files NRR reading cc:
L. Engle ICSB reading J. Roe T. Ippolito 3g*
C. Miller M. Srfnivasan
-NCB,'/
P. Rosa A. Szukiewic:
__ DSS; IfSB_
B op..
- ASzuWe
- . _..Cli11er. _
.we....
..2/9/k.___..
2/$/77 m.*
Forse AEC 314 mee. 9 53) AECM 0240 W u. a. oovannuen resanne oprics ina.sae.ies 800205 01%
t
ENCIDSURE A DABIS BESSE INIT 1 TEONICAL SPECIFICATION CONENTS 1.
Core Flooding Tank Isolation Valves page 3/4 5-1 Operability applicability should include mode 4 with the reactor coolant pressure greater than 800 psig.
{
8 2.
Page 3/4 5-2 Item C should read as follows:
At least once per 31 days by verifying that the power to the isolation valve operations is disconnected and the breakers are locked spen in the open position.
3.
Page 3/4 5-2 One of the diverse instrument string for the DHR isolation valve (i.e. Ill 11 and IH 12) interlocks does not originate from the SFAS instrument strings therefore the technical specifications should specify that the calibration of the following instrument string snould be perfonned at least once every 18 months, i.e. for pressure switch PSH 7531 A.
4.
'Ihe interlock instrument strings for the SFRCS system PSL 4928A,B (less than 12 psig)
PSL 4929A,B (less than 12 psig)
PSL 4930A,B (less than 11 psig) should be identified in the surveilance requirements for modes 1 through 4.
Functional checks should be performed monthly.
Instrument calibration should be performed every refueling.
Ese instmnent strings should be identified in Table 3.3.11, and the set point trip valves rnould be identified in Table 3.3.12.
. ~
~
5.
Include in the SFRCS instrument strings the auxiliary-steam generator level control instruments, if-SP9A4, LC-SP9A3 LC-SP9B3, LC-SP9B4 Functional checks should be perfomed monthly.
Instrument calibration 8
should be performed every refueling.
These instn: ment strings should be identified in Table 3.3.4, and the setpoint trip valves should be identified in Table 3.3.12.
6.
Include in the SFRCS instrument strings the following:
PSL 1060 PSL 107D PSL 106B PSL 107B PSL 106C PSL 107C PSL 106A PSL 107A Rese switches actuate 0 less than 10 psig. H e surveillance require-ments should be inclussive from mode 1 to mode 4.
Functional checks should be performed monthly. Instnment calibration should be perfonned every refueling.
7.
He sensors referred to in note 4, 5 and 6 are identified an drawing 7749 - K)5O Revision 9 and 7749 - M051 Revision 11. Note also that the level switch item numbers identified on page 3/4 3-25 and 3/4 3-26 are different than what are shown an the above " latest" drawings.
The applicant should correct these discrepancies.
8.
Le response times given in Table 3.3.5 do not appear to be reasonable for some of the items listed.
It appears that in some cases the response times listed do not include the response times for the diesel generator
3 and/or the sequence timers. %ese tables should be revised to n flect the actual as built design, i.e. if the actuators are pneumatic then the l
diesel generator or sequence timers response time may not be required l
in the total response time requirements.
a 9.
He RCS pressure instnanent strings for the ECCS system listed in Table 4.3-2 should require 120 day calibration period and not at each refueling (as indicated), if these transmitters are the same type as the transmitters used for the RPS system than exhibit drift. Refer to our discussion in section 7.2 of the SER and correct accordingly.
- 10. Page 3/4 3-23 The applicability mode for the SFRCS system should include mode 4.
Check this requirement out with PSB.
- 11. The technical specification requirement review for; Section 3/4 3/4 (Radiation Monitoring), incore detectors, seismic detectors. Meterological instrumentation is beyond ICSB review. R ese sections should be reviewed by the cognizant reviewer in AAB, MEB respectibely.
- 12. The equipment listing for accident and post accident monitoring instrumentation is incomplete. Table 7.8 provides the list of equipment required for surveilance (denoted by double asterics) they are:
1.
R. C. loop outlet temperature 2.
R. C. loop pressure 3.
Pressurizer level
- 4. Steam generator start-up range level 8
5.
Auxiliary feedwater status 6.
Containment vessel isolation status 7.
Safety features equipment status 8.
RPS status 9.
SFRCS status
- 10. High pressure flow
- 11. Low pressure injection flow
- 12. HPI system pump and valve status
- 13. LPI system pump and valve status
- 14. Containment spray pump and vilve status 15'.
Containment emergency punp valve status
- 16. BWST valve status
- 17. Containment air recirculation fan status
- 18. Containment air fan status
- 19. Emergency ventalation system fan and damper status
- 13. Enclosed is a marked-up copy of the technical specification sections refered in your memo of January 12, 1977, with additional editorial coments for your consideration (see Enclosure B).
.