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Amend 146 to License DPR-49,revising Tech Specs Re Identification of Appropriate Containment Purge & Vent Valves to Operation of Containment Purge & Vent Valves When Plant at Power & to Valves Closure Times
	ML20235S467
Person / Time
Site:	Duane Arnold
Issue date:	09/30/1987
From:	Virgilio M; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20235S470	List: ML20235S467; ML20235S478;
References
	NUDOCS 8710090012
	Download: ML20235S467 (9)
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NUCLEAR REGULATORY COMMISSION.

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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOP ERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331-DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 146 License No. DPR-49 1.

The Nuclear Regulatory Comission (the Commission) has found that:

A.

The application for amendment by Iowa Electric Light and Power Company, et al, dated December 18, 1986, which superseded a r,ubmittal dated April 5, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and. regulations set forth in 10.CFR Chapter I; 8.

The facility will operate in conformity with' the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authorized-by this amendment can be conducted without endangering the health t

i and safety of the public, and (ii) that such activities will be 1

conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements.

have been satisfied.

2.

Accordingly, the license. is amended by changes.to the Technical Spec'iff-cations as indicated in the attachment to this license amendment;and paragraph 2.C.(2)ofFacilityOperatingLicenseNo.DPR-49~isherebyj amended to read as follows:

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s-e Technical Specifications

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The Technical Specifications contained in Appendix A, as revised through Amendment No.146 ;- Wre hqrety incorporated in the license.

The licensee shall operate.the facility in accordance with the Technical Specifications'.

3.

The license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.

3 FGR THE NUCLEAR REGULATORY COMMISSION,<

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~#. M Martin J.>Virgilio, Director w.

Project Directorate III-1 0 vison of Reactor Projects - III, IV, V & Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: September 30, 1987

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ATTACHMENT TO LICENSE AMENDMENT NO.146 p

i FACILITY OPERATING LICENSE NO. DPR-49 l

I ji DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines.

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3.7-22 1

3.7-23 I

3.7-24 i

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DAEC-1 J.,

SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION __

7.

(Deleted) 7.

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8.

If the specifications of 3.7. A.1 through 3.7. A.5 cannot be met, an orderly shutdown shall be initiated and the reactor shal1 be in a cold

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shutdown condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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Purging

.j Containment vent / purge valves (CV-4300, CV-4301, CV-4302, CV-4303, CV-4306, CV-4307, CV 4308, CV-4309, and CV-4310)

L may not be opened so as to i

create a flow path from the 1

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primary containment while PRIMARY CONTAINMENT INTEGRITY 1s required except for inerting, de-inerting, vent / purge valve testing,. or 2

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pressure control.

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u4 Amerldment No. JM, 777,146 o1 -.

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DAEC-1 LIMITINGCOGITIONFOROkERATION-SURVEILLANCE REQUIREMENT by partial closure and.

subsequent reopening, d.

At least once per operating

cycle the operability of the reactor coolant system instrument line flow check valves shall be verified.

2.

With one or more of the primary containment isolation valves shown in Table 3.7-3 inoperable (except for those exempted as noted in Table 3.7-3), maintain at least one isolation valve OPERABLE **or ISOLATED ** *and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

a. Restore the inoperable valve (s) to OPERABLE status, or

b. Isolate each affected penetration by use of at least one automatic valve locked or electrically deactivated in the isolated position,***or

c. Isolate each affected penetration by use of at least one manual valve locked in the isolated position or blind flange.***

3.

If Specification 3.7.D.1, and 3.7,0.2 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the COLD SHUTDOWN condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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- This valve may be locked or electrically deactivated as noted in subsection 3.7.D.2.b.

- - Isolation valves closed to satisfy

Intent Change Only (definition of L

these requirements may be reopened operatingcycle),

on an intermittent basis under administrative control.

O Amendment No. M. 345,1146 S

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1)AEC 1 TABLE 3.7-2 CONTAINMENT ISOLATION VALVES SUBJECT TO TYPE C TEST REQUIREMENTS PENETRATION #

SYSTEM BOUNDARY VALVES 4

7A Main Steam Line CV-4412, 4413 4

78 Main Steam Line CV-4415, 4416 4

7C Main Steam Line CV-4418, 4419 4

70 Main Steam Line CV-4420, 4421 8

Main Steam Line Drain M0-4423, M0-4424 9A Feedwater & HPCI Feed V-14-3 9A2 Feedwater & HPCI Feed M0-4441, M0-2312 98 Feedwater V-14-1 982 Feedwater & RCIC Feed & RWCU Return M0-2740, M0-4442, M0-2512 10 RCIC Condensate Return CV-2410, CV-2411 10 Steam to RCIC Turbine M0-2400, M0-2401 11 Steam to HPCI Turbine M0-2238, M0-2239 11 HPCI Condensate Return CV-2211, CV-2212 15 RWCU Supply M0-2700, M0-2701 16A Core Spray Pump Discharge M0-2115, M0-2117 16B Core Spray Pep Discharge M0-2135, M0-2137 j

19 Drywell Floor Drain Discharge CV-3704, CV-3705

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20 Demineralized Water Supply V-09-65. V-09-111 21 Service Air Svpply V-30-287, Blind Flange 22, 229 Containment Compressor Discharge CV-4371A, CV-4371C, V-43-214 3

23A, B3 Well Cooling Water Supply CV-5718A, CV-57188, V-57-75 V-57-76 3

24A, B3 Well Cooling Water Return

, CV-5704A, CV-57048, V-57-77 V-57-78 4

CV-4302 5, CV-43035 CV-4310 l 25 Drywell Purge Outlet CV-4306 CV-4307,5,, CV-4308,5 26, 220 Drywell and Torus Purge Supply 5

4 4

26, 220 Orywell and Torus Nitrogen Makeup CV-4311, CV-4312, CV-4313 Amendment No. 79E, 77), 7ff,146 3.7-22 CIfJ a

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TABLEJ.7-2 (Continued)

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CONTAINMEN' 130LATION VALVES SUBJECT 10 TYPE C TEST REQUIREMENTS PENETRATION #

SYSTEM BOUNDARY VALVES 320 Containment Compressor Suction CV-4378A, CV-4378B i

32E Recirc Pump "A" Seal Purge V-17-96, CV-180.4B 32F Recirc Ptsnp "B" Seal Purge V-17-83, CV-1804A 35A,B,C D T.I.P Drives T.I.P Ball Valves and Check Valve on X-35A 361 CRD Return V-17-53, V-17-52, V-17-54 39A Containment Spray / CAD Supply SV-4332A, SV-4332B l

398 Containment Spray / CAD Supply SV-4331A, SV-43318

' 40C,0 Post-Accident Sampling / Jet Pump Sample SV-4594A, SV-45948, SV-4595A, SV-45958 4

41 Recirc Loop Sample CV-4639, CV-4640 42 Standby Liquid Control V-26-8, V-26-9 46E 02 Analyzer SV-8105B, SV-81063 48 Drywell Equipment Drain Discharge CV-3728, CV-3729

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SOB 02 Analyzer SV-8101A, SV-8102A, 50E 02 Analyzer SV-8103A, SV-8104A, 500 02 Analyzer SV-8105A, SV-8106A p

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543 Reactor Building Closed Cooling Water Return M0-4841A U

553 Reactor Building Closed Cooling Water Supply MO-4841B 56C 02 Analyzer SV-8101B, SV-8102B, 56D 02 Analyzer SV-8103B, SV-8104B 4

5 205 Torus Purge Outlet CV-4300,5CV-4301,

l CV-4309 211A Torus Spray / CAD Supply SV-4333A, SV-4333B 211B Torus Spray / CAD Supply SV-4334A, SV-4334B 2121 RCIC Turbine Exhaust 4

V-24-8 V-24-23 V-24-46, V-24-47 l

2141 HPCI Turbine Exhaust V-22-16 V-22-174 V-22-63, V-22-64 i

Amendment No. 7pp.,173,17E,146 dn,an.u.u 4 3.7-23

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i NOTES TO TABLE 3.7-2 1

l 1 est volume is filled with demineralized water then pressurized to 1.10 P, T

with air or nitrogen for test. For all other penetrations (except 7A-0), test l'

volumes are pressurized to P with air or nitrogen for test.

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l 2M0-4441 M0-4442 will be remote manually closed.

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1 3 n accordance with 10 CFR 50, Appendix A, General Design Criterion 57, the I

redundant barriers are a single isolation valve outside containment and a closed system inside. Testing of the single isolation valve only is required.

' Manual valves V-57-75, V-57-76, i.57-77 and V-57-78 will be normally locked e-closed.

4 Tested in reverse direction.

1 SDuring Type C testing, it shall be verified that the mechanical modification which limits the maximum opening angle is intact.

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The main steam line isolation valves are functionally tested on a

.I more frequent interval to establish a high degree of reliability.

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The containment is penetrated by a large number of small diameter instrument lines. The excess flow check valves in these lines shall be tested once each operating cycle.

Containment vent / purge valves (CV-4300, CV-4301, CV-4302, CV.-4303, CV-4306, CV-4307, and CV-4308) have been mechanically modified to limit the ir.aximisn opening angle to 30 degrees.

This has been done to ensure these valves are able to close against the maximum differential pressure expected to occur during a design basis accident.

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Intent Change Only (definition of operating cycle).

. Amendment No. 70, 146 3.7-48

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ML20235S467

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