ML19319C665

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Amend 44 to Application for Ol,Incorporating Revision 27 to Fsar.Table of Contents for FSAR Revision Encl
ML19319C665
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 04/25/1977
From:
TOLEDO EDISON CO.
To:
Shared Package
ML19319C664 List:
References
NUDOCS 8002200779
Download: ML19319C665 (6)
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Text

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\\v g f.at:rfi I.'*l3 APPLICATION FOR LICENSES FOR

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DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Docket No. 50-346 Amendment No. 44 Enclosed herewith amending the above application are sixty (60) copies of Revision No. 27 to the Final Safety Analysis Report (FSAR). This revision updates the FSAR to include all of the changes and commitments made prior to obtaining Operating License NPF-3 on April 22, 1977.

By Vice President, Facilities Development Sworn to and subscribed before me, this 25th day of August 1977.

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D-B FCAR RWISTO'i 27 CONTENTS (Sheet II TECo to NRC Letter PIAR Pap, Serial No./Date Subject Comments 3-185 299/3-2-77 Containment vessel pressure transmitters environmentai quallrication 4-34.35 232/3-2-77 Reactor Vessel Surveillance Program Clarified surveillance specimen program 5-53.kk 232/3-2-77 Reactor Vessel Surveillance Program Clarified surveillance specimen program 5-101 (deleted)

, 232/ 3-2-T7 Table 5-25lREactorYesselMaterialIrradfatten Neplaced 1:7 Tech Spee Tatle %;%-5 Surveillance i

Figure 5-24 (delete)232/3-2-77 Pressure Vessel Neutron Fluence During Operation BePlaced by Tech Spec Bases Figure k-1 of Typiesl Plant l

s 6-h6.47.48.kBa 235/3-3-77 Lines penetrating containment vessel Heorganization for clarlfication 6-k8a 235/3-3-77 DH suction line penetrating containment rescription erpanded for clarification 6-49.50.51.52.53 235/3-3-77 Table 6-8. Containment Vessel Isolation Valve Arrangements Consistency with FSAR test and Tech. Specs.

6-75a 262/k-7-77 Table 6-16. ECCS Single Failure Analysis Address dose rate due to water recirculated 6-85.86.87 235/3-3-77 to BWST post.

ECCS tests and inspections Consistency with Tect.. Specs.

7-28 198/1-26/77 SFAS testing Delete reference to automatic testing i

feature 7-33e 31h/7-6-77 and Main steam line pressure Correct margin to be consistent with aet-300/6-2k-77 related points r,d allowable values 7-k6 260/4-7-77 and DH suction valves auto closure setpoint References subsection 7 6.1.1.2 (p 7-kT) 271/5-2-77 related for details 7-h7.47a 260/L-7-77 &

DH suction valves auto closure setpoint Descrites temporary raising of setpoint and 2T1/5-2-77 determination of setpoint Telecon F. Miller /0.

Commits to conditions consistent with Mazetis of k-27-77 license Describes permanent pressurizer heater trip interlock 7-kib 260/h-7-77 Tage carryover 7-Sh 26C/k-7-77 and 271/5-2-77 related DH suction valves auto closure setpoint References subsection 7.6.1.1.2 for details 7-86 261/k-7-77 related Table T-3. RPS Trip Setting Limits Addresses allowable values for both channel calibration and channel functional test-ing; update response times; corrects y

errors in setting limits 7-88.89 261/&-6-77 related Table 7-5. SFAS Actuation Summary Addresses allowable values for bott. channel 265/h-7-77 related calibration and channel functional test-ing; CV radiation setpoints and allowable values to be set at two times background.

determined after full-power; revised BWST level values; revises essential bus volt-age values, adds DH isolation valve interlock T-91 255/h-h-77 &

Table 7-7. SFAS Performance Requirements CV radiation range to be determined after 265/k-7 full power 7-9 3.9ha 255/k-4/77 &

Table 7-8. Information Readouts CV radiation raage to be determined after 265/4 7/77 full power 7-98 31k/7-6-77 Table 7-11. SFBCS Settings Addresses allowable values for both channel 308/6-2h-77 calibration and channel functional test-ing; adds setpoints and allowable values for loss of RCPS (previously undefined value)

T gure T-hA.LB 260/k-7-77 related Manual trip button on control board Dws F16. sh 1 and th 2 changed to maintained; added pressuriter heater interlock and instrument numbers

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  • i PSAR REVISION 27 CONTENTS (Sheet 2}

TEco to NRC Letter FStR Pan.

Serial No./Date Subject Cosysent s Figure T AA,B,C,D 260/k-7 s7 Added interlock with pressurizer heaters Dwg E 52B, oh 2kA, 2kB 240 and 2kD Figure T-30 261/4-6-77 related Power / Imbalance / Flow Trip Setpoing Provides definitive values (referenced from Table T-3)

Figure T-31 261/h-6-TT related Power / Imbalance / Flow Allowable Values Provides definitive values (references from 7l Table T-3) 8-10 293/T-18-77 Udvvoltage relays Change time delay to 9 seconds

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A 8-21a(1) 2k6/3-23-TT Eivt rical noise / fault testing for SFAS and RPS Describes test program to demonstrate ade-I through and 282/5-25-77 quacy of noise rejection for credible 8-21a(9) el.ectrical faults in non-IE systems 8-21a(10) 246/8-23-71.nd 282/

Page carryover i

5-25-TT related I

8-21c & 8-21d 258/4-18-77 Cables run in raceway Justification of mixing functions in raceways l

l 8-21d 195/1-26-77 Tray fill Justification for exceeding side rails /

inclusion of thermal insulation B-21e 258/b-18-77 High energy equipment in calbe spreading room Rating of lighting transformer chemged 8-23a Telecon 2-15-77 M.

Electrical penetration protection Provide diversity of control voltage to Calcamuggio and A.

insure trip of backup breaker u!on loss Szukiewicz of control voltage to local breaker 1

8-32 Telecon 2-15-T7 M.

Table 8-3, Administrative 1y Controlled Circuits (DC)

Add trans*ar switch in implementation of Calcamuggio and A.

diversity of control voltage for busses A Szukiewicz and B of 13.8 kV switchgear Figure 8-6 291/T-18-T7 Added b under voltage relays on each b.16 kV (Dwg. E3, Rev 8) 175/12-21-76 safety-related bus 179/1-h-T7

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11gure 8-11 Telecon 2-15-TT Changed description of control voltage feeders (Dwg. E-T)

M. Calcamuggio and to 13.3 KV switehgear A. Szukiewicz 9-83 260/k-7-77 and 271/

DH suction valves auto closures References subsection T.6.1.1.2(p-7-hT) for details 5-2-77 related Deletes reference to removal of power 9-83a 260/h-7-TT and 271/

DH suction valves auto closure 5-2-T7 related 4

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FSAR REVISION 27 C0lrIENTS (Sheet 3)

TECo to NRC Letter FSAR Page Serial bio./Date Subject Comments

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12-17 255/k-L-77 &

Table 12-3,' Area Radiation Monitors Containment vessel essential monitor (used 4

265/k-7-77 for AFAS) setpoint to be detemined after full pcver operation 14-96 203/1-28-77 Tahle 14 3, Post criticality Testing Inder Added reactor coglant systes natural f

circulation teet i

ik-99 337/8-1-77 Zero Power Physics Test Requirement not applicable to Davis-Besse i

Unit 1 1 l 14-103 203/1-28-77 Reactor Coolant System Natural Circulation Test To meet requirements of R.G.1.68

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15-5h Telecons F. Miller /G.

Mazetis of April 7.13,1k Ioss of feedvater accident Updated to be consistent with current design and 15 discussed in the appropriate sections of the FSAR 15-106 Same as page 15-54 Steam line break accident-Clarify assumptions of negative reactivity injection by HPL 15-120 273/5-6-77 Fuel handling accident Added discussion of fuel handling accident through inside containment 15-121b(3) 6.2.2k-2 30k/6-15-77 (related)

Pressure test of emergency ventilation system Update to describe test performed 8.1.2-2 258/k-18-77 Electrical separation Changed lighting transformer to 30 kVA 8.3 1-6 257/k-7-77 Protection of emergency diesels from fires Changed to photoelectric smoke detectors 9 5.k-1 & 9 5.k-2 257/k-7-77 Fire protection in areas where oil may be used Cla f f ed flame det

added system 15 1.T-1 261/4-6-77 related Parameters to initiate auxiliary feedwater Corrected values to be consistent with Tech.

Specs.

15.2.12-3 &

263/h-7-T7 Main feedwater line break Clarified mass and euergy release to be from 15 2.12.h the SG Figure 15 2 12-6,

-10 & -14 15 2.12-7 263/k-7-77 Main feedvater line break Updated closure information for feedwater

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stop valve; clarified worst cases for (1) core effect and (2) containment pressure 15 2.12-Ta 263/4-7 T related Page carryover 15.4.1-2 same as y 2 15-54 Steam line areak accident Documents requirement to have HPI 35 seconds after the break to ensure sub-criticality during cooldown below 550 F 15.4.1-3 same as page 15-5h Steam line break accident Addresses loss of offsite power 15.4.1-6 &

same as page 15-5h steam line break accident Justifies HPI injection time for loss of e

15.4.1-6a offsite power and no loss of offsite pwar cases 15.k.1-8 same as page 15-5h Steam line break Change feedwater stop valve closures time to 17 seconds P7 1.1-k &

260/k-T-TT DH suction valves References section 7.6.1.1.2 for da. ails of P7 1.1-5 &

setpoint=' interlock P7.6.3-2 t

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L-B DIRECTIONS FOR INSERTING REVISION 27. AUGUST 1977 During insertion of the revised pages, a dash (-) in the renove or insert column of the directions means no action is required. Asterisks (*) at the lef t of the instructions indicate an additional clarification at the end of the directions. The page revision indexes go in front of the spplicable chapter or appendix.

a RDOVE INSERT VOLUME 2 age Revision Index (Chapter 3)

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