W3P84-1136, Verifies That Design,Const & Testing of Facility Completed Per FSAR & Unit Will Be Ready to Load Fuel by 840530. Activities Which May Not Be Finished by 840530 & Anticipated License Conditions Encl.Granting OL Requested

Verifies That Design,Const & Testing of Facility Completed Per FSAR & Unit Will Be Ready to Load Fuel by 840530. Activities Which May Not Be Finished by 840530 & Anticipated License Conditions Encl.Granting OL Requested

ML20084C564
Person / Time
Site:	Waterford
Issue date:	04/25/1984
From:	Leddick R LOUISIANA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NS20153, W3P84-1136, NUDOCS 8404300095
Download: ML20084C564 (10)

Text

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P O W E R & L i G H T! Now once Ana tous4NA m ee meo 70 4 74 noon e mcw aoo vi.rs UTILiflCS SYSTEM April 25, 1984 ROTH S LEDDICK Senior Vico President Nuclear Operations W3P84-1136 3-A1.16.07 Mr. Ilarold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555

SUBJECT:

Waterford SES Unit 3 Docket No. 50-382 Plant Readiness for Fuel Load

Dear Mr. Denton:

Louisiana Power and Light is submitting this letter to verify that the design, construction and testing of Waterford SES Unit No. 3 has essentially been completed in accordance with the Final Safety Analysis Report and other licensing documents, and that the unit will be ready to load fuel by May 30, 1984.

The attachments to this letter identify those activities that are incomplete at this time, but do not preclude issuance of an operating license and/or fuel loading. These activities, along with those which remain open but will be completed prior to issuance of an operating license, will continue to be performed and tracked in accordance with established procedures to ensure that licensing requirements are met.

Louisiana Power and Light Company has concluded that the incomplete status of the items included herein at the time of fuel loading and/or low powcr testing will have no adverse impact to the safe operation of the plant or the health and safety of the general public. Additionally, the Safety Review Committee (SRC) for Waterford 3 has reviewed the attachments for their safety significance.

Louisiana Power and Light Company therefore requests that an operating license be granted for Waterford 3.

ym rs very truly, b c Sr. Vice President, Nuclear Operations ljl RSL/ RAS /lbg 9404300095 040425 PDft ADOCK 05000392 h PDR m

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Hr. Harold Denton, Director (

W3P84-ll36  !

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Attachments: I -

Activities which may not be completed by May 30, 1984. i I

II - Anticipated Conditions of License.

III -

Initial Test Programs / Systems which may not be f completed / accepted by core load. j l

IV - Significant Construction Deficiencies for which  !

corrective action may not be completed by May 30, 1984. ,

V -

I & E findings for which corrective actions may not l l

be completed by May 30, 1984.

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cc: Mr. G. W. Knighton, NRC - Bethesda l Mr. D. M. Crutchfield, NRC - Bethesda  !

Mr. J. T. Collins, NRC - Region IV  !

Mr. J. Wilson, NRC - Bethesda '

Mr. G. L. Constable, NRC - Waterford 3 i Hr. E. L. Blake  ;

Mr. W. H. Stevenson i t

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l ATTACHMENT I Activities which may not be completed by_ Hay __30, 1984

1) Anticipated Conditions of License (Refer to Attachment !!).

2) All initial test programs / systems required for Fuel Load (LI'&L letter W3P84-0735, K. W. Cook to G. W. Knighton, March 20, 1984) shall be under control of the Plant Staf f prior to loading fuel. In addition, those systems not required to support fuel loading which may not be accepted by Ny 30, 1984 are listed in Attachment !!!.

3) Significant Construction Deficiencies (SCD).

(Refer to Attachment !!).

4) I & E Findings (Refer to Attachment V).

5) All open items required for entry into Mode 6 will be completed prior to loading fuel, i

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ATTACHMENT II Anticipated Conditions of License

1. Maximum Power Level Louisiana Power and Light Company is authorized to operate the facility at reactor core power levels not in excess of 3390 megawatts thermal (100%) power.

2. Technical Specifications and Environmental Protection Plan The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. Antitrust Conditions Louisiana Power and Light Company shall comply with the antitrust conditions of the license.

4. Fuel Rod Pressure Approval Only Up to 39.1 GWd/t (Section 4.2.2.2, SER)

The licensee shall not exceed 39.1 GWd/t rod-average burnup for its CE 16 x 16 fuel.

5. LER Required on Spurious Operation or Malfunction of Megawatt Demand Setter (MDS) or Reactor Power Cutback System (Section 7.7.3.3, SER)

The licensee shall report inadvertent or spurious operation or m.lfunction of the MDS or Reactor Power Cutback system for at least the first two fuel cycles of operation. Subsequently, the licensee may review and submit-the-operating experience gained with these systems and request relief from the reporting requirement.

6. Single Failure of Control System (Section 7.7, SSER 1)-

Prior to startup after the first' refueling outage, the licensee must conduct a review to identify any power sources or sensors which provide power or signals to two or more control systems and to

' demonstrate that failure or malfunctions of their power sources or sensors will not result in consequences outside of the bounds of FSAR -

[ analyses or beyond the capability of operation of safety systems.

7. Initial Inservice: Inspection Program (Section 6.6, SSER 5) -

Within 6 months after reaching commercial operation,:the licensee must.

submit an. initial inservice inspection program for staff review and approval.

'8. Environmental Qualification (Section 3.'11, SSER 5)

LP&L shall environmentally qualify all electrical equipment as required by 10 CFR 50.49.

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(' ) ATTACIMENT Il'(CONT'D) ', "

1 Anticipated Conlitions of the Licens=

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9. AxialGroddi(SectirJX4.2,SSER5)  ;

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The issue:of shoulder gap clearance in CE 16 x 16\ fuel mt:st be resolved ls before the second cycle of operation for Waterford 3. 3hould generic resolution not be reached before the second cycle, the staff will h consider favorable visual surveillance results for a representative s

r 3 ,s sample of the assemblies.

10. I!edvy Loads (Section 9.1.4, SSER 5) - i '

3 Prior'to startup following the s'ecdnd reideling outage, LP&L shall have ks, 3 nade colnmit:ihnts acceptable to the NRC stdff regarding any changes and

'modificatiori3 required to fully satisfy the guidelines of Sections

! i.1.2 through 5.1.6 of NUREG-0612s(Plase II: nine-montt0 responses tch

., l the NRC Generic Letter on control of lieavy loads,' dat'ed' December 22,

.i o1 1980). -

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11. -IVR Startup or Operating Experience (Section 13, SSER 6) ,

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During the startup test program, the'licen<see shall l$ ave on each shift a licensed individual with previods s.tartup or operati'ng experience on a comparable PWR, or an advisor,who m'eets these experience requirements. ( r

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-12. Emergency Preparedness (CectCon 13.3, SSER 5) r ,

a. s Satisf actory FEMA sup'plemental findings #and ' determinations

, of 'offsite'prepareeness must be submidted before' exceeding x ,5% of rated ~ power. '

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, Before operatiott, above 5% of rated powe'r, . the licensee N .'Ishall comply 4 th the requirements o6 10 CFR 50.47(a)

,y ~4h(c)andAppendixE,sSectionIV.F,regardingemergency

'-s preparedness' exercises.

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In the eventi that the NRC' finds that the lack of progress

~in completiorXof the procedures in the Federal Emergency

.i'. s Management Agency's final rule,'44 CFR Part 350, is an

indication that Wmajor substantive problem exists . in O achieving 'or maintaining an adequate state of preparedness, the provisions'ofr10 CFR Section 50.54(s)(2) will apply.

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134 Fire Protection (Section 9.5.1, SSER S)

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.The li,censee shall maintain in effect all provisions of the approved fire protedtion program.  ; i

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ATTACHMENT II (CONT'D)

Anticipated Conditions of the License

14. Initial Test Program (Section 14, SER)

The licensee shall conduct the post-fuel-loading initial test program described in Chapter 14 of the FSAR, as amended, without making any major modifications unless such modifications have prior NRC approval.

15. Emergency Response Capabilities (Generic Letter 82-33, Supplement 1 to NUREG-0737 LP&L shall complete the following emergency response capabilities no later than the following dates:

a. Safety Parameter Display System fully 5% Power operational and operators trained.

b. Detailed Control Room Design Review January 31, 1985 (Program Pl'an/ Summary Report Submittal) 4 4

ATTACHMENT III Initial Test Programs / Systems which may not be Completed / Accepted by Core Load System No. System Description Priority 13B Heat Tracing Non-Safety Post Fuel Load 15 Start-up Test SPO-120 Post Fuel Load 32 Sump Pumps Drainage Post Fuel Load 40-08 Turbine Gantry Crane Post Fuel Load 40-10 SGFP Crane Post Fuel Load 45 Misc. Area HVAC Post Fuel Load 46B3 RAB Toxic Chemical Monitors Post Fuel Load 46H RAB Misc. HVAC Post Fuel Load 54-1 Post Accident Sampling System Post Fuel Load 55G Solid Waste Mgnt.-Post Startup Post Fuel Load 55J1 Filter Transfer Post Fuel Load 55K1 Portable Demin Taps Post Fuel Load 55K2 Additional Waste Tankage Post Fuel Load 71C Condensate Polishing Post Fuel Load 72C ,

Auxiliary Feedwater Pump Post Fuel Load 4

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r ATTACHMENT IV

< Open Significant Construction Deficiencies which may not be Completed Prior to May 30, 1984 SCD-37 Temperature Detecters (RTD's) failure. (Post-Core Hot Functional Testing) - ECD-07/15/84.

SCD-57 Inadequate I & C installation and turnover documentation. ECD-05/20/84.*

SCD-60 Turnover Documentation and Inadequate hanger weld problems. ECD-05/25/84.*

SCD-80 Unsatisfactory stroking of EFW pump turbine steam shutoff valve. (Post-Core Hot Functional Testing) -

ECD-07/13/84.

SCD-93 Charging and letdown containment isolation valve deficiencies (Post-Core Hot Functional Testing) -

ECD-07/01/84.

l. SCD-105 Electrical Separation Deficiencies. ECD-05/23/84.*

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• LP&L Action Complete PriorITo May 30, 1984. NRC Closure May-Be Pending On May 30, 1984.

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ATTACHMENT V I & E Findings for which Corrective Actions may not be Completed Prior to May 30, 1984 Number Description ECD 82-11-09 Air cleaning system incomplete. 05/30/84*

82-11-12 Transportation activities. Prior to Radwaste Shipment - 12/31/85 82-12-10 Post Accident Sampling System 5% Power - 06/15/84 (PASS).

83-08-22 Post Accident Sampling and Analysis 06/08/84 Equipment.

i 83-08-24 Containment air sampling and 06/08/84 analysis equipment.

83-08-38 Make provisions and include 12/84 arrangements for additional

, telephone service.

83-08-62 Emergency notification in high 08/01/84 noise areas.

83-08-115 Dissemination of Emergency 07/16/84 information to the transient population.

83-08-116 Operational testing of siren 07/16/84 warning system.

84-02 Finalize Lesson Plans for 06/15/84 training offsite personnel.

84-02-04 Revise the training lesson plan 06/15/84

~for dose assessment.

84-02-05 Include hierarchy for the 06/15/84 selection of meteorological data into EP-2-050.

• ' LP&L Action Will Be Complete Prior To Initial Criticality.

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ATTACHMENT V (CONT'D)

I & E Findings for which Corrective Actions may not be Completed Prior to May 30, 1984 Number Description ECD 84-02-06 The same units for specifying 06/15/84 meteorological tower heights should be used in both the procedures and control room displays.

84-02-07 Additional walkthroughs with 06/15/84 control room personnel should be performed for EP-2-050, EP-2-051 and EP-2-052.

84-05-02 NUREG-0737 (Item II.B.3) 06/15/84 Post Accident Sampling Capability, l

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