ML20049A776

Application for Amend to License NPF-3,revising App a Tech Specs Re Steam Generator Containment Isolation Valves, Chlorine Detector & Control Room Ventilation & I-131 Dose Equivalent.Safety Evaluations Encl

ML20049A776
Person / Time
Site:	Davis Besse
Issue date:	09/25/1981
From:	Crouse R TOLEDO EDISON CO.
To:
Shared Package
ML20049A770	List: ML20049A769 ML20049A776 ML20049A784
References
TAC-47040, TAC-47041, TAC-47043, NUDOCS 8110020261
Download: ML20049A776 (6)

Text

l '. .

APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR F0WER STATION UNIT NO. 1 Enclosed are forty-three,(43) copies of the requested changes to the Davis-Besse Nuclear Poves Station Unit No. 1 Facility Operating License No. KPF-3, together with the Safety Evaluation for the requested change.

The proposed changes include: 4

1. Changes in Table 3.6-2 (Steam Generator Containment Isolation Valves);

2. Changes in Bases 3/4 3.3.7 (Chlorine Detector and Control Room Ventilation);

3. Changes in Section 4.4.6.2.2 and 6.9.1.9 (Combined Lenkage Test and Reporting Requirements);

4. Changes in Section 3.4.8, Table 4.4-4, Figure 3.4-1 and Bases (Dose Equivalent I-131).

By [ __

Vice President, Nuclear Sworn to and subscribed before me this @ day of  ! t/_A, ,j [.

j ,

=

Notar/Public LAURIE A. BRUDZINSKI

( _

Notary Public, State of Ohio bj a/10 Ny Commissai Egiros May 16,1986

'8110020261 010925' PDR ADOCK 05000346

.. p PDR

't. .

F .

t Docket No. 50-346 License No. NPF-3 Serial No. 738 Sep'tember 25, 1981 Attachment I I. Change to Davis-Ecsse Nuclear Power Station Unit 1, Appendix A, Technical Specificatiot.2, Table 3.6-2.

A. Time required to Impler, ant This change is to be effective upcn NRC approval and subsequent removal of the valves. l B. Reason for Change. (Facility Change Request 78-126A) l The valves are 'aing removed. Technical Specifications for i the valves are no longer required.

C. Safety Evaluation See attsched t.

bj a/11

SAFETY 7 VALUATION This licenae amendment request proposes deletion of valves MS603A and MS611A from Technical Specifications Table 3.6-2 and deletion of asterisks frcm salves MS603 and MS611 in this table.

The safety function of valves MS603A and MS611A as contair. ment isolation valves is to isolate the containment from the outside environment it the event of a release of radioactive material to the conta!.nment atmosphere.

These valves are also required to maintain steam generr. tor isolation to preserve the heat removal capability of the steam generators.

Valves MS603A and MS611A are being removed from the steam generator blow-down system. Valves MS603 and MS611 (which MS603A and MS611A bypass), will be provided with an automatic steam and feedwater rupture control system (SFRCS) half trip close signal to isolate the steam generators in the event of a loss of feedwater, steam line break or feedwater line break. The asterisk on these valves in Technical Specifi-cations Table 3.6-2 indicates that these valves "may be opened on an intermittent basis under administritive control". Since automatic SFRCS closure (half trip) is being provided for these valves, this restriction is no longer necessery. Thus the asterisks from valves MS603 and MS611 in Table 3.6-2'can be deleted. Also, since valves MS603A and MS611A are being deleted from the system, they should also be deleted from Technical Specifications Table 3.6-2. By making the above changes, the safety function achieved by these valves remains unaffected.

Pursuant to the above, it is concluded that the Technical Specifications changcs proposed by this License Amendment request do not involve an unreviewed safety question.

bj a/12 l

l

~ , . . _ . _ _ _ _ . . _ _ _ _ _ _ . - - . . , _ ,. .. . . _ ,_ ._ - _ . . _ _ _ _

7/// W V. 6;r.2 .

. CONTAINMENT ] SOLATION VEyES (ConM.nued)

~

IS0!.ATION PENETRATION VA!.YE .

TIME NUMBER HUMBER_ FUNCTION Refueling Canal Fill Line .

N/A 49 DH87 '

Refueling Canal Fill Line N/A 49 DH88 High Pressure Injection N/A 50 f HP48 RCP Seal Water Supply N/A 52 MU242 RCP Seal Water Supply N/A 53 MU243 RCP Seal Water Supply N/A S4 MU244 RCP Seal Vater'. Supply N/A

, # 55 MU245 N/A g 7! MS603

. - wn Steam Generator Drain Line a i.cs.m u tne re w r u r e a n L T DC -

M /A w/,

p si,m .- ---f~~ ,

p Bf M5611 Steam Generator Drain Line JA bra-h We . __ - N/A 31

@- v . ~ ~ y~

Secondary Side Cleaning (Inside 59 Flange. N/A Containment) 5.0 Fitnge Secondary Side Cleaning (Outside

- Contairrnent) N/A .

Hydrogen Dilution System Supply N/A 67 CY209 Nydrogen Dilution System Supply N/A E9 CY210 N/A 71A i CY20005 Containment Pressure Sensor -

tic CF16 Core Flood Tank Nitrogen Fill N/A Line -

N/A 72A ! CV20015 Containment Pressure Sensor ,

l 72C ! CV6245 Containment Pressure' Differential N/A Transmitter N/A 73' ! CV2002B Containment Pressure Sensor 13C. i CV645B Containant Pressure Differentiai N/A Transmitter Containment Pressure Sensor

. N/A 74A ! CV20033 Pressurizer Auxiliary Spray N/A

• 740 DS2735 Pressurizer Auxiliary Spray N/A

+74C DH2736 Tay be opened on an intercittent basis under administrative control.

(Not subject to Tyre C leakage tests. ,

" Surveillance testing not recuired prior to entering MODE 4 but shall be performed prior to entering Mode 3.

!iProvisions of Specification 3.0.4 are not applicable provided the valve is in the closed positions and deactivated.

3/4 6-22 Amendment No. g, 31 DAVIS-BESSE, UNIT 1

Docket No. 50-346 License No. NPF-3 ,

Serial No. 738 September 25, 1981 Attacl - ant 2 ,

I. Change to Davis-Besse Nuclear Power Station Unit 1, Appendix A, Technical Specifications Bases 3/4.3.3.7. .

A. Time required to Implement This change is to be effective upon NRC approval.

B. Reason for Change (Facility Change Request 81-179)

To correct sa error in Technical Specifications Bases.

C. Safety Evaluation See attac'aed.

bj a/13 l

l

's - - . - - -- - . - , , _ _ . _ . . _ , , _ _ , . , , . _ . _ . . _ _ _ , . _ , . _ , , _ _ . , , _ _ , . _ _ , _ _ , _ _ _ _ _ _ _ , ,, _ _ _ _ . . , , , , ,,

- 1 Safety Fvaluation l

I Propose change to the Davis-Besse Technical Specifications bases Section 3/4.3.3.7 to read as follows:

"The operability of the chlorine detection systems ensures that an i accidental chlorine release will be detected promptly and the control room will be automatically isolated. The control room ventilation system will be manually started in the recirculation mode to provide the required prorection. The chlorine detection systems required by this specification are consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operations Against an Accidental Chi.orine Release", February, 1975".

The safety function of the chlorine detection systems is to promptly detect and initiate protective action to safeguard the control room personnel in the event of an accidental chlorine release. The change 3'

proposes to rectify an errer found in bases Section 3/4.3.3.7 of the Technical Specifications. Section 9.4.1.3 of the Final Safety Analysis Report (FSAR) st:tes that it is the clorine detection systems (not the control room emergency ventilation system as stated in the above section

. of the Technical Specifications bases), that automatically isolate the control room if chlorine concentrations in the air exceed the detector setpoint. Signals from the chlorine detectors will stop the normal

~

operating fans, and cause the normal ventilation system intake, exhaust, and control room isolation dampers to close.

Since the safety function of the chlorine detection systems is not affected by this change, it is concluded that no unreviewed safety question is involved, bj 'a/14 2

e

- , , --. . _y. ,c ., r-e.. m , _ m-- - . . - . - - --,. ., - -