ML20133F094

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Re Vent & Purge Isolation Valve Mod
ML20133F094
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 10/02/1985
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20133E980 List:
References
NUDOCS 8510100119
Download: ML20133F094 (8)
v • d • e


Text

m

[-.

ATTACHMENT-B PROPOSED CHANGE TO APPENDIX A TECHNICAL SPECIFICATIONS T0 OPERATING LICENSE tPF-11 REVISED PAGES: 3/4 6-15 3/4 6-25 3/4 6-34 3/4 8-27 8 3/4 6-2 0701K P

1

/ .s j ... . - . . . .

CONTAINMENT SYSTEMS DRWELL AND SUPPRESSION CHAMBER PURGE SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber purge system may be in operation I bt with the drywell and/or suppression .r... . . in... chamber

",0". Purging purge supp t

iLet : :-h ' _ "..cfi , .;'.. 1 . Lt .. i. J . . .. ... i i. a through the Standby Gas Treatment System shall be restricted to less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days.

OPERATIONAL CONDITIONS 1, 2 and 3.

- APPLICABILITY: .

ACTION:

With a drywell and/or suppression chamber purge supply and/or14exhaust but isolation valve open for other than inerting, de-inertingdor in pressure l- contro er ::t b!:: Erd t: 1ere t h - ::::1 t within one hour or be in at least HOT SHUTDOWN within the next 12 COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS supply ~

-0.0.1.0.1 '." hen teing .p....J, t.h. 4,f 11 e..J e yp..e..;;ien ; 7;.4Li.% L. pLivoi.a . ..-

i seheletien .;' .;; ehell h

d d :::t battr "3 ",0* epen, ealee; se erified within the t:  ;;;; t; i.;; then er ev,el te pr=f::: 3'. d:y:.

-4.5.1.*.  !;eh dri ell and e.ppr.;;ien et -te. p.cse e ppi, end exheest Schtha Je' Je ; hell L. 4 ;enetreted O'C'nA"LE .t 1 e.i vin...per butt r'l lL3 4;rifying thet the sensered leakese rete is isss-thea er equal-to-

^2J.g:

k 4.6.1.8./ The cumulative time that the drywell ifand sup shall be verified to be less than or equal to 90 hours0.00104 days <br />0.025 hours <br />1.488095e-4 weeks <br />3.4245e-5 months <br /> per 365 days prior to use in this mode of operation. .

Amendment No.18 3/4 6-15 LA SALLE - UNIT 1

TABLE 3.6.3-1 (Continued) 5 PRIMARY CONTA1HREP.T ISOLATION VALVES

> MAXIMUM E

" 150LAT10ft IIRC VALVE GROUP _I") (Seconds) _

VALVE FUNCTION ANO NUMBER

[

Automatic Isolation Valves (Continued) -

w 4

8. Containment Vent and Purge Valves # < 10
  • l IVQO26 7 10*a IVQO27 IVQO29 7 10**j
IVQO30 I lofy IVQO31 -

7 5 ,,,JL-IVQO32 7 104*J IVQO34 p i IVQO35 w IVQO36 7 1C **

.1 IVQ040 7 10,a *j 710W

!m IVQ042

~

E IVQ043 j* IVQ047 35 IVQ048

  • IVQ050 35

<5 i IVQ051 .

IVQ068 9 R.A. l
9. RCIC Tu 1 Exhaust Vacuum Breaker 1E51-F080 1E51-F086

.10. LPCS, HPCS, RCIC, RHR Injection III 2 N.A. g Testable Check Bypass Valves '

1E21-F333 i .

[ 1E22-F354 5 1E12-F327A, 8, C 3 z IE51-F354

. IE51-F355 i 4 .

r s

. ~

/- -

a .

TABLE 3.6.3-1 (Continued)

- PRIMARY CONTAINMENT ISOLATION VALVES.

r .

I F

m VALVE FUNCTION At:0 NLSBER e Other Isolation Valves (Continued)

E 7. Post LOCA Hydrogen Control ,

~ ,

  • IHG001A, 8

" 1HG002A, 8 1HG005A, 8 ~

1HG006A, 8

8. Standby Liquid Control System IC41-F004A, 8 1C41-F007 l l 9. Reactor Recirculation Seal Infection ***

w 1833-F013A, B IdI i 1833-F017A, B II) i 10. Drywell Pneumatic System

% IIN018 1

  • But > 3 seconds.

(a) See Specification 3.3.2, Table 3.3.2-1, for isolation signal (s) that operates each valve group.

(b) Not included in total sum of Type 8 and C tests.

(c) May be opened on an intermittent basis under administrative control.

(d) Not closed by SLCS actuation.

(e) Not closed by Trip Functions Sa, b or c, Specification 3.3.2, Table 3.3.2-1.

(f) Not closed by Trip Functions 4a, c, d, e or f of Specification 3.3.2, Table 3.3.2-1.

(g) Not subject to Type C leakage test.

(h) Opens on an isolation signal. Valves will be open during Type A test. No Type C test required.

(1) Also closed by drywell pressure-high signal.

[ (j) Hydraulic leak test at 43.6 psig.

s (k) Not subject to Type C leakage test - leakage rate tested per Specification 4.4.3.2.2.

g (1) These penetrations are provided with removable spools outboard.of the outboard isolation valve.

s During operation, these lines will be blind flanged using a double 0-ring and a type B ieak

" test. In addition, the packing of these isolation valves will be soap-bubble tested to ensure f insignificant or no leakage at the containment test pressure each refuelino outane. p g *_* Ihese valves shall have a maximum isolation time of 40 seconds ustil STARillP following first refuelina outaae.

      • The specified 18-month interval may be waived for Cycle 1 provided the surveillance is performed during Refuel 1.

TABLE 3.8.3.3-1 .

MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICE SYSTEM (5)

VALVE NUMBER (Continuous)(Accident Conditions) AFFECTED

a. IVG001 Accident Conditions SBGTS IVG003 Accident Conditions -

2VG001 Accident Conditions 2VG003 Accident Conditions

b. IVP113A Accident Conditions Primary containment IVP113B Accident Conditions chilled water coolers IVP114A Accident Conditions IV?l14B Accident Conditions IVP053A Accident Conditions I 1VP0538 Accident Conditions IVP063A Accident Conditions IVP0638 Accident Conditions
c. IVQ000 A.

_[.VQjjj k w.u nw gunw . q unt 9

J. .x.',% %'.;%,

. 7'M 9'?? I"."u

,,m...u. . '? ".."*

.. u.

Accident Conditions Id IVQO38 IVQ001 A..: dent Oenditien; 1 IVQO32 Accident Conditions

~

VQOT A;;iin 0;nditi;n
l IVQO35 Accident Conditions A;;ii nt 0;nditi;n:

-IVQ027 IVQ040 A;;ii nt 0;nditi;n:

IVQ000 A;;iint 0;nditi;n; IVQ047 Accident Conditions IVQ04B Accident Conditions IVQu50 Accident Conditions IVQ051 Accident Conditions IVQ068 Accident Conditions A;;ident 0;nditien; I.

-1VQ000 IVQO37 Accident Conditions Accident Conditions RBCCW system

d. 1WR179 IWR180 Accident Conditions 1WR040 Accident Conditions 1WR029 Accident Conditions
e. Accicent Conditions Main steam system 1821 - F067A 1821 - F0675 Accident Conditions 1821 - F067C Accident Conditions 1821 - Fa67D Accident Cor.ditions 1B21 - FM9 Accid?nt Conditions '

1821 - Fc16 Accident Conditions LA SALLE - UNIT 1 3/4 8-27 Amendment No. 18

/  ;

CONTAINMENT SYSTEM.S 8ASES 3/4.6.1.5 PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the maximum pressure of 45 psig in the event of a LOCA. The measurement of containment tendon lift-off force, the tensile tests of the ,

tendon wires or strands, the visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, the chemical and visual examination of the sheathing filler grease, and the Type A leakage test are sufficient' to demonstrate this capability.

The surveillance requirements for demonstrating the primary containment's structural integrity and the method of predicting the pre-stress loses are in

. compliance with the recommendations of Regulatory Guide 1.35.1, " Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures,"

January 1976, and proposed Regulatory Guide 1.35.1, " Determining Prestressing M Forces for Inspection of Prestressed Concrete Containment Structures,"

April 1979 with the following clarification: the tested lift-off force of individual tendon tension shall be greater than or e' qual to the initial pre-stress minus the loses, as predicted in the as-built design, which occur between the initial pre-operational structural integrity test and the time of subsequent surveillance..

The required Special Reports from any engineering evaluation or contain-ment abnormalities shall include a description of the tend 6n condition, the condition of the concrete (especially at tendon anchorages), the inspection if procedura, the tolerances on cracking, the results of the engineering evalua-tion, and the corrective action taken.

i 3/4.6.1.6 DRYWELL AND SUPPRESSION CHAMBER INTERNAL PRESSURE The limitations on drywell and suppression chamber internal pressure ensure that the containment peak pressure of 39.6 psig does not exceed the design pressure of 45 psig during LOCA conditions or that the external pres-sure differential does not exceed the design maximum external pressure differen-tial of 5 psid. The limit of 2.0 psig for initial positive primary containment pressure will limit the total pressure to 39.6 psig which is less than the

[ design pressure and is consistent with the accident analysis. ,

1

! 3/4.6.1.7 DRYWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that the l

containment pahk air temperature does not exceed the design temperature of l 340*F during LOCA conditions and is consistent with the accident analysis.

3/4.6.1.8 DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM l The drywell and suppressiori chamber purge supply and exhaust isolation I valves are required to be closed during plant operation except as required l

for inerting, de-inerting and pressure control. Unti-lTchest valves have been l demonstrated capable of closing during a LOCA or steam line break accidentp thQ shell be bie d ed se es net te epen se.e then 50".- -

l ,

frex We. k t o p {cs.H oAh LA SALLE - UNIT 1 8 3/4 6-2 Amendment No. 1 8 l

I

- , - - - - n.-------,.,,. . . -,.,.,,_,,,m,. - -- .

ATTACHWNT C SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specifi-cation Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated because the new vent and purge isolation valves replace the existing isolation valves one for one. No additional valves have been added. The new valves meet the requirements for vent and purge containment isolation valves.

This amendment simply remcves requirements which only apply to the valves being removed.

'2) - Create the possibility of a new or different kind of accident from any accident previously evaluated because the modification does not effect the containment isolation valve arrangement.

3) Involve a significant reduction in the margin of safety because the design still meets the intent of General Design Criteria 56 as specified in the UFSAR.

Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system or component, the consequences of prsviously evaluated accidents will not be increased and the margin of safety will not be decreased. Therefore, based on the guidance provided in the Federal Register

-and the criteria established in 10 CFR 50.92(e), the proposed change does not constitute a significant harards consideration.

070lK

.. - J r" ATmcamewr 2>

r, potel engineers potel enfErprises, inc.

7

>MmE 3400 blue soring rd. nw suite b-3 p. o. box 3531 huntsville, claborno 35810 205-859-5000 L

June 18, 1985 Commonwealth Edison Company Rural Rt. 1 Box 220 Marseilles, IL 61341 Attention: Mr. Tom Hammerick

Subject:

Qualification of Clow Purge and Vent Valves 8-Inch and 26-Inch

Reference:

Clow Job Number 84-2842(N)

PEI Job Number 8522 S&L Spec. No. T-3750, Issue, " Bid" Gentlemen:

as Per our telecon of 6/18/85 the following Patel reports will be used basis for qualification of the subject valves:

1) " Qualification Report of Clow 8-Inch and 26-Inch Wafer Valves Assemblies," Clow Job Number 84-2842-(N), CECO 26":

Valve Tag Numbers 8": IVQ042, -43, 2VQ042, -43, 1VQO26, -27, -29, -30, -31, -34, -36, -40, 2VQO26, -27,

-30, -31, -34, -36, -40.

2) " Seismic Qualification Analysis of Clow 26-Inch Wafer Stop Valve," Patel Engineers Technical Report No.

PEI-TR-852200-1, dated April 8, 1985.

I

3) " Seismic Qualification Analysis of Clow 8-Inch Wafer ,

Stop Valve," Patel Engineers Technical Report No.

PEI-TR-83-24, Revision A, dated July 18, 1984.

4) " Seismic Qualification Status Report on Clow Wafer l

Valves, GH-Bettis Valve Actuators, and Associated '

l Control Components," Patel Engineers Technical Report l No. PEI-TR-852201-02, dated April 15, 1985.

If you have any questions or comments, please feel free to call.

! Sincerely

/ /  %

N. Allen Davidson Nuclear Power Services NAD/jb cc: Mr. Steve Nondahl, Clow Corporation

!

Retrieved from "https://kanterella.com/w/index.php?title=ML20133F094&oldid=2881316"