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| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC |
| | page count = 2 | | | page count = 2 |
| | | project = TAC:63534 |
| | | stage = Other |
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| a TA Duqu@esne U@t (412)393-7546 Beaver Valley No. 2 Unit Project organization Telecopy (412) 393-7889 S.E.G. Building P.O. Box 328 Shippingport, PA 15077 2 NRC-7-146 l | | a TA Duqu@esne U@t (412)393-7546 Beaver Valley No. 2 Unit Project organization Telecopy (412) 393-7889 S.E.G. Building P.O. Box 328 Shippingport, PA 15077 2 NRC-7-146 l |
| i l May 26, 1987 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 | | i l |
| | May 26, 1987 United States Nuclear Regulatory Commission ATTN: |
| | Document Control Desk Washington, D. C. |
| | 20555 |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Containment Instrument Air System & Accumulator Isolation Valve Tests Gentlemen: | | Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Containment Instrument Air System & Accumulator Isolation Valve Tests Gentlemen: |
| In order to resolve the Pre-Operational Testing issues the following tests will be performed after core loading but prior to criticality: | | In order to resolve the Pre-Operational Testing issues the following tests will be performed after core loading but prior to criticality: |
| : 1) Design verification of the Containment Instrument Air System.
| | 1) |
| : 2) Safety Injection Accumulator discharge isolation valve j test. l This correspondence supersedes those statements made in DLC Letters 2 NRC-7-140 and Item # 1 of 2 NRC-7-141, both dated May j 1 25, 1987. '
| | Design verification of the Containment Instrument Air System. |
| DUQUESNE LIGHT COMPANY, By J. @/. CareyV l Senior Vice President 1 1 | | 2) |
| 8705280428 870526 l PDR ADOCK 05000412 i l P PDR j l l | | Safety Injection Accumulator discharge isolation valve j |
| f'u I | | test. |
| | l This correspondence supersedes those statements made in DLC Letters 2 NRC-7-140 and Item # 1 of 2 NRC-7-141, both dated May j |
| | 1 25, 1987. |
| | DUQUESNE LIGHT COMPANY, By J. @/. CareyV l |
| | Senior Vice President 1 |
| | 1 8705280428 870526 l |
| | PDR ADOCK 05000412 i |
| | l P |
| | PDR j |
| | l f'u l |
| | I |
|
| |
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| J | | J o |
| . o United States'. Nuclear Regulatory Commission.
| | United States'. Nuclear Regulatory Commission. |
| Containment Instrument Air System & Accumulator Isolation Valve Tests Page 2 I | | Containment Instrument Air System & Accumulator Isolation Valve Tests Page 2 I |
| cc: Mr. P. Tam, Project Manager Mr. J. Beall, NRC Sr. Resident Inspector Mr. L. Prividy, NRC Resident Inspector INPO Records Center i | | cc: |
| | Mr. P. Tam, Project Manager Mr. J. Beall, NRC Sr. Resident Inspector Mr. L. Prividy, NRC Resident Inspector INPO Records Center i |
| 1 4 | | 1 4 |
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Letter Sequence Other |
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Results
Other: ML20195H593, ML20196A791, ML20206C051, ML20213G384, ML20213G443, ML20214J058, ML20214J923, ML20214K398, ML20214K734, ML20214L962, ML20214M147, ML20216C555, ML20234C237, ML20235R591, ML20236H213, ML20238A152
|
MONTHYEARML20214J9231986-08-0808 August 1986
Forwards Response to Item in Technical Evaluation Rept Re Testing Program,Per SER Open Item 9
Project stage: Other
ML20206C0511987-04-0606 April 1987
Forwards Revised FSAR Section 14.2.12.8.13, Pressurizer Heater Spray Capability Test (Ist), Scheduled to Be Included in FSAR Amend 17 (May 1987).Rev Describes Contents of IST-2.06.2 & Incorporates Previous Ref Commitment
Project stage: Other
ML20213G3841987-05-12012 May 1987
Advises That Exception on FSAR Table 1.8-1,Amend 5,revised in Amend 10 to Resolve NRC Question 640.10 Requesting List of air-operated Valves to Be Excluded from Loss of Instrument Air Test
Project stage: Other
ML20213G4431987-05-12012 May 1987
Submits Resolution of NRC Comments on Changes Made to FSAR Section 14.2, Initial Test Program, in Amend 13
Project stage: Other
ML20214M1471987-05-21021 May 1987
Informs That Util Will Amend FSAR Section 14.2.12.66.2, Containment Air Recirculation Sys Test, to State That Containment Air Temp Will Be Recorded at 5%,50% & 100% Reactor Power Levels Using Installed Sensor Sys
Project stage: Other
ML20214L9621987-05-21021 May 1987
Informs That SER Confirmatory Item 52C Re Plant Performance Following MSIV Closure Will Be Completed W/Reactor Producing 30% Rather than 100% Power Due to Possibility of High Power Level Leading to Unnecessary Sys Conditions
Project stage: Other
ML20214K7341987-05-21021 May 1987
Provides Clarification of Util 870512 Response to NRC 870311 Questions Re Changes to FSAR Section 14.2 on Initial Test Program.Table 1, Equivalent Tests, Encl
Project stage: Other
ML20214J0581987-05-25025 May 1987
Advises That Util Does Not Consider NRC Concern Re Cycling Open Safety Injection Accumulator Isolation Valves,Valid Per Reg Guide 1.79.Util Administrative Controls Require Valves to Be Open W/Power Removed from Control Circuit
Project stage: Other
ML20214J0301987-05-25025 May 1987
Submits Supplemental Info to Items 4 & 8 of Util 870521 Response to NRC Comments Re Changes Made in FSAR Section 14.2, Initial Test Program. Air Receiver Vol Test Not Required Since Instrument Air Sys Not safety-related
Project stage: Supplement
ML20214K3981987-05-26026 May 1987
Informs of Tests to Be Performed After Core Loading Prior to Criticality in Order to Resolve Preoperational Testing Issues
Project stage: Other
ML20216C5551987-06-23023 June 1987
Informs That Util Completed Test STP-2.11.01 Which Verified That Accumulator Isolation Valves Open Against Max Differential Pressure (SER Confirmatory Item 51A)
Project stage: Other
ML20235R5911987-07-14014 July 1987
Forwards Status Rept Identifying Changes to Initial Test Program as Described in FSAR Chapter 14,per 10CFR50.59
Project stage: Other
ML20238A1521987-08-17017 August 1987
Forwards Second Status Rept Identifying Changes to Initial Test Program Described in Chapter 14 of Fsar.Changes Made in Accordance W/Provisions of 10CFR50.59
Project stage: Other
ML20204J3111987-08-28028 August 1987
Discusses Request for NRC Approval of Revised Power Ascension Test Schedule,Per 870825,26 & 27 Discussions.Rev Required Temporary Deferral of IST 2.21.A.02, MSIV & IST 2.04.03, Turbine Trip W/Loss of Offsite..
Project stage: Request
ML20234C2371987-09-15015 September 1987
Forwards Third Status Rept Identifying Changes to Initial Test Program as Described in FSAR Chapter 14.Changes Made Per Provisions of 10CFR50.59(b)
Project stage: Other
ML20236H2131987-10-27027 October 1987
Forwards Fourth Status Rept,Identifying Changes to Initial Test Program Described in Fsar,Chapter 14,per 10CFR50.59(b)
Project stage: Other
ML20195H5931988-01-0707 January 1988
Forwards Sixth Status Rept Identifying Changes to Initial Test Program as Described in Chapter 14 of FSAR
Project stage: Other
ML20196A7911988-01-29029 January 1988
Fowards Seventh Status Rept Identifying Changes to Initial Test Program Described in Chapter 14 of Fsar.Changes Made in Accordance w/10CFR50.59 within 1 Month of Initiating Changes Per OL Condition C.(3)
Project stage: Other
1987-05-26
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a TA Duqu@esne U@t (412)393-7546 Beaver Valley No. 2 Unit Project organization Telecopy (412) 393-7889 S.E.G. Building P.O. Box 328 Shippingport, PA 15077 2 NRC-7-146 l
i l
May 26, 1987 United States Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D. C.
20555
SUBJECT:
Beaver Valley Power Station Unit No. 2 Docket No. 50-412 Containment Instrument Air System & Accumulator Isolation Valve Tests Gentlemen:
In order to resolve the Pre-Operational Testing issues the following tests will be performed after core loading but prior to criticality:
1)
Design verification of the Containment Instrument Air System.
2)
Safety Injection Accumulator discharge isolation valve j
test.
l This correspondence supersedes those statements made in DLC Letters 2 NRC-7-140 and Item # 1 of 2 NRC-7-141, both dated May j
1 25, 1987.
DUQUESNE LIGHT COMPANY, By J. @/. CareyV l
Senior Vice President 1
1 8705280428 870526 l
PDR ADOCK 05000412 i
l P
PDR j
l f'u l
I
J o
United States'. Nuclear Regulatory Commission.
Containment Instrument Air System & Accumulator Isolation Valve Tests Page 2 I
cc:
Mr. P. Tam, Project Manager Mr. J. Beall, NRC Sr. Resident Inspector Mr. L. Prividy, NRC Resident Inspector INPO Records Center i
1 4
-l l
1 k
m,._
.e r -...-.-