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Amend 84 to License NPF-29,changing TS & Bases for Containment Purge Sys Replacing Cumulative Time Limitation on Sys Operation w/safety-related Criteria
	ML20086S892
Person / Time
Site:	Grand Gulf
Issue date:	12/17/1991
From:	Larkins J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20086S896	List: ML20086S892; ML20086S899;
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	NUDOCS 9201060050
	Download: ML20086S892 (6)
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NUCLEAR REGULATORY COMMISSION I

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ENTERGY OPERATIONS. INC.

SYSTEM ENERGY _ RESOURCES. INC.

SOUTH f,ISSISSIPPI, ELECTRIC POWER ASSOCIATION MISSISSIPPI POWER AND__ LIGHT COMPANY DOCKET NO. 50-41,6 GRAND GULF NUCLEAR STA'fl0N. LINIT 1 M'ENLMENT_ TO FACILI,TY OPERATING LICENSE Amendment No. 84 License No. NPF-29 1.

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

A.

The application for anendment by Entergy herations, Inc. (the licensee) dated May 10, 1991, conplies wit i the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The f acility will operate in conformity with the application, the previsions of the Act, and the rules and reguhtions of the Commissioni C.

There is reasonable assurance (1) that thE ectivities authorized by this acendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

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

The issuance of this anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirerents have been satisfied.

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Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendmentt changes to paragr?nh 2.C.(2), and deletion of paragraph 2.C.(16) of Facility Operativ; License No. HPf-29 is hereby amended to read as follows:

(2) Technical Specifteations The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as ravised through Amendment No. 84, are hereby incorporated into this license. Entergy Operations Inc. shall operate the facility in accordance with the Techn} cal Specifications and the Environmental Protection Plan.

(16) Containment Purge (Section 6.2.4 SSER #5)

(Deleted) 3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMIS$10N John T. Larkins, Director Project Directorate IV.1 Division of Reactor Projects 111, IV, and V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Spee.ifications Date of Issuance: December 17. 1991 1

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G ATTACHMENT TO LICENSE AMENDMENT NO. 84 FACILITY OPERATING LICENSE NO NPF-29 DOCKET NO. 50-416 Replace the following pages of the License and the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment nunber and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness, REMOVE PAGES INSERT PAGES License page 8 License page 8 3/4 6-12 3/4 6-12 B 3/4 6-2 B 3/4 6-2 1

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(b) Natural circulation shall be prohibited as an operating mode.

(14)-LoosePartsMonitoring(Section4.4.1,SER)

Prior to startup following the first refueling outage, MP&L shall submit an evaluation of the loose parts monitoring system to address conformance to Regulatory Guide 1.133 Revision 1, dated May 1981.

(15) Scram Discharge Volume (Section 4.6, SER)

Prior to startup following the first refueling outage MP&L shall incorporate the following additional modifications into the scram discharge volume system:

(1)- Redundant vent and drain valves, and (ii) Diverse and redundant scram instrumentation for each instrumented volume, including both. delta pressure sensors and float sensors. -

(16) psntainment Purge (Section 6.2.4, SSER #5)

-(Deleted)

(17) Containment Pressure Boundary (Section 6.2.8, SER)

Prior to startup following the first refueling outag6, MP&L shall replace the feedwater check valve disc with a disc made from a suitable material.

(18) Pressure Interlocks on Valves interfacing at Low and High Pressure (Section 6.3.4, 55ER f2)

Prior to startup following the first refueling outage, MP&L shall implement isolation protection against overpressurization of the-low pressure emergency core cooling systems (RHR/LPCI and LPCS) at the high and lo;; pressure interface containing a check valve and a closed motor-operated valve.

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Amendms..it No. 6, 84

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i C_0N1AINMENT SYSTEMS CONTAINMENT AVERAGE AIR TEMPERATURE LIMITING CONDITION FOR OPERATION i

3.6.1.8 Containment average air temperature shall not exceed 90'F.

APPLICABillTY:

OPERATIONAL CONDITIONS 1, 2 and 3.

A_CTION:

With-the containment average air temperature greater than 90'F, reduce the average air temperatura to within the limit within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT $HU100WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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$URVEILLANCE REQUIREMENf5

4. 6.1. 8 The containment average air temperature shall be the arithmetical average of the temperatures at the following locations and shall be determined to be within the limit at least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

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Elevation Azimuth a.

s119'-0" 20'<A <70 -

i b.

s119'-0" 110*7A 7160' c.

N119'-0" 200'7A 7250

d.

s119'-0" 290'7A 7340*

e.

s139'-0" 20*IA 770' f.

s139'-0" 110*7A 7160' g.

s139'-0" 200'7A 7250' i

h.

s139'-0" 290 7A 7340" i

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s208'-0" 20'7A 770' J.

s208'-0" 110*7A 7160' K.

s208' 0" 200'7A 7250' i

290 7A 7340*

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%208'-0" l

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-s240'-0" 20'7A 770' i

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s240'-0" 110 7A 7160' 240'-0" 200 7A 7250' o.

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s240'-U" 290*5A5340 l

l GRAND GULF-UN11 1 3/4 6-11 i

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4 CONTAINMENT SYSTEMS CONTAINMENT PURGE SYSTEM LIMITING CUNDITION FOR OPERATION 3.6.1.9 The containment > urge system supply and exhaust isolation valves shall be OPERABLE and eitler the 20 inch or the 6 inch

) urge system may be in o>eration; however, the 20 inch purge system shall not ye in operation nor sla11 the 20 inch valves be open except for containment pressure control for orforsurveillance ALARA and air quality considerations for personnel entry, isolation valve or special testing on the pur0e system that requires the be open.

A_PPLICABillTY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a.

With a containment purge system supply and/or-exhaust isolation valve (s) inoperable except for the condition covered in Action C l

close the inoperable valve (s) or othervice isolate the penetration (s) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

With the 20 inch supply and/or exhaust isolation valve (s) open except as allowed by Specification 2.6.1.9 or otherwise isolate the penetratior$(close the open 20 inch valve (s) s) within four hours or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN with-in the following 24 nours.

With a containment purge supply and/or exhaust isolation valve (s)-

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vith resilient material seals having a measured leakage rate exceed-ing the limit cf Surveillance Requirement 4.6.1.9.2, restore the in-operable valve (s) to OPERABLE status or otherwise isolate the )ene-tration(s) so that the measured leakage rate does not~ exceed tie limit of Specification 4.6.1.9.2 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least I

HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.1.9.1-At least once per 31 days each 20 inch-containment-purge system supply and exhaust isolation valve shall be verified closed,*

4.6.1.9.2 At least once per 92 days each containment purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE by verifying that the measured leakage rate is less then or equal to 0.01 L, when pressurized to P '

a

However, the valves need not be closed and may be open as allowed by Specifica-tion 3.6.1.9.

GRAND GULF-UNIT 1 3/4 6-12 Amendment No. 84

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRlHARY CONTAINMENT 3/4.6.1.1 PRlHARY CONTAINHENT INTEGRITY PRIMARY CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.

This restric-tion,inconjunctionwiththeleakageratelimitation,willlimitthesite boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.

,3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the acchot analyses at the peak accident pressure of 11.5 psig, P,

As an added conser-vatism, the measured overall integrated leakage rate il further limited to less than or equal to 0.75 L during performance of the periodic tests to account for possible degradation of,the containment leakage barriers between leakage tests.

Operating experience with the main steam line isolation valu s has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.

The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J to 10 CFR 50 with the exception of exemption (s) granted for testing the airlocks af ter each opening, 3/4.6.1.3 CONTAINMEN1Allt0CKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY and the containment leakage rate given in Specifications 3.6.1.1 and 3.6.1.2.

The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation. Only one closed door in each air lock is required to maintain the integrity of the containment.

Verification that each air lock door inflatable

-seal system is OPERABLE by the performance of a local leak-detection test for

t. period of less than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months is permissible if it can be demonstrated that the leakage rate can be accurately determined for this shorter period.

(This is in accordance with Sections 6.4 and 1.6 of ANSI N45.4-1972.)

3f/,4. 6.1. 4 MSIV-LEAKAGE CONTROL SYSTEM Calculated doses resulting from the maximum leakage allocme fr the main steamline isolation valves in the postulated LOCA situations would be 3 small fraction of the 10 CFR 100 guidelines, provided the main steam line sys'.em from the isolation valves up to and including the turbine condenser remains intact.

Operating experience has indicated that degradation has occasionally occurred in the leak tightness of the HSIV's such that the specified leakage requirements have not always been maintained continuously.

The requirement for the leakage control system will reduce the untreated leakage from the HSIVs when isolation of the primary system and containment is required.

GRAND GULF-UNIT 1 B 3/4 6-1 l

CONTAINMENT SYSTEMS BASES i

i 3/4. 6. L 5 FEEDWAIER LEAKAGE CONTROL SYST_EM The feedwater leakage control system consists of two independent subsystems designed to eliminate through-line leakage in the feedwater piping by pres-surizing the feedwater lines to a higher pressure than the containment and i

drywell pressure.

This ensures that no release of radioactivity through the feedwater line isolation valves will occur following a loss of all offsite power coincident with the postulated design basis loss-of-coolant accident.

t 3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY I

This limitation ensures that the structural integrity of the containment vill be maintained comparable to the original design standards for the life of the unit.

Structural integrity is required to ensure that the containment will withstand the maximum pressure of 11.5 psig in the event of a LOCA.

A visual 1

inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.

3/4.6.1.7 CONTAINMENT INTERNAL PRESSURE The limitations on containment-tn-Auxiliary Building and Enclosure Building i

differential pretsure ensure that the containment peak pressure of 11.5 psig does not exceed the design pressure of 15.0 psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differential of 3.0 psid.

The limit of -0.1 to 1.0 psid for initial containment-to-Auxiliary Building and Enclosure Building differenti(I pressure will limit the containment pressure to 11.5 psid which is less tnan the design pressure and is consistent with the safety analysis.

3/4.6.1.8 CONTAINMENT AVERAGE AIR TEMPERATURE The limitation on containment average air tem)erature ensures that the containment peak air temperature does not exceed t1e design temperature of 185 F during LOCA conditions and is consistent with the safety analysis.

3/4.G.I.9 CONTAINMENT PURGE SYSTEM

.The continuous use of the containment purge lines during all operational conditions is restricted to the 6-inch purge supply and exhaust isolation valves

whereas, continuous containment purge using the 20-inch purge system islimItedtoonlyOPERATIONALCONDITIONS4and5.

Intermittent use of the 20-inch purge system during OPERATIONAL CONDITIONS 1, 2 and 3 is restricted to the following:

i a.

Containment pressure control, b.

-ALARA and air quality considerations for personnel entry due to:

high explosive gas concentration, low oxygen concentration, high air-

. borne particulate activity, high gaseous radioactivity, smoke or fumes, or Surveillante or special testing on the purge system that requires

c..

the isolation valve (s) to be open.

The design of the 6-inch purge supply and exhaust isolation valves meets the requirements of Branch Technical Position CSB 6-4, " Containment Purging During Normal Plant Operations."

GRAND GULF-UNIT 1 8 3/4 6-2 Amendment No. 84 1

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ML20086S892

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