Similar Documents at Surry |
---|
Category:Drawing
MONTHYEARML20034F0532020-01-31031 January 2020 Proposed License Amendment Request: Allowed Outage Time Extension for Replacement of Reserve Station Service Transformer C 5KV Cables to Transfer Bus F Response to Request for Clarification and Additional Information ML19105B0552019-04-15015 April 2019 Superseded Pages Per Revision No. 01 to Environmental Sampling Program ML0501805082004-07-19019 July 2004 Associated System Drawings in Support of North Anna Power Station Units 1 & 2, and Surry Power Station Units 1 & 2, ASME Section XI Inservice Inspection Program End of Intervals System Pressure Testing ML0413302072004-05-0505 May 2004 Drawing 11548-FM-1E, Rev 10, Machinery Location Reactor Continment Sections A-A, X-X & F-F Surry Power Station - Unit 2. Sheet 1 of 1 ML0413302082004-05-0505 May 2004 Drawing 11548-FM-1F, Rev 9, Mach. Loc. Reactor Cont. Sections B-B. E-E. Y-Y & Z-Z Surry Power Station - Unit 2. Shet 1 of 1 ML0413302092004-05-0505 May 2004 Drawing 11548-FM-10, Rev 9, Mach Loc Reactor Cont Sections C-C & D-D Surry Power Station - Unit 2. Sheet 1 of 1 ML0414804032004-01-30030 January 2004 Drawing 11448-FE-7B, Rev 21, Wiring Diagram Annunciator (ANN-VSP) Surry Power Station - Unit 1. Sheet 1 of 1 ML0414804142002-05-29029 May 2002 Drawing 11448-FB-27A, Rev 16, Plumbing and Fire Protection Service Building Surry Power Station - Unit 1. Sheet 1 of 1 ML0414804152002-01-31031 January 2002 Drawing 11448-FB-25E, Rev 22, Ventilation & Air Conditioning Service Building - El. 9' - 6 Surry Power Station - Unit 1. Sheet 1 of 1 ML19095A2821978-02-22022 February 1978 Response to Request for Information on LOCA Pipe Break Inside Reactor Vessel Cavity ML19095A2841978-02-15015 February 1978 Presenting, Unit 2 Steam Generator Surveillance Program Outage Schedule & Information of Program ML19093B0471977-12-23023 December 1977 Request for NRC Review of Test Performance Data on Defense Apparel Air Hood & for Permission to Continue Using of Hood Indicated by VEPCO Letter of 12/6/1977 with Serial No. 558 ML19093B0821977-12-0101 December 1977 Response to a Letter of 09/14/1977 Regarding the Potential for a Boron Dilution Accident at Surry Unit Nos. 1 & 2 Due to Injection of Contents of Naoh Tank Into Reactor Coolant System ML19093A9671977-09-0101 September 1977 Letter Serial # 374 Dated 08/29/1977 Provided Information Regarding NPSH Available for Lead Safety Injection Pumps at Surry. Determined That Procedures Should Be Implemented to Throttle Valves in Lhsi Pump Discharge ML19098B4441977-06-28028 June 1977 Provide Requested Information Relative to Site Settlement to Close Previously Unresolved Item Identified as 76-15/1, Site Settlement Surveillance ML19095A5541977-01-11011 January 1977 Submit Licensee Event Report No. AO-S1-76-08 Re Broken Stud from 2A Steam Generator Girth Strap with Unit 2 ML19105A1811975-12-31031 December 1975 Submit Supplement to Initial Report Dated 12/4/1975, Which Responded to IE Bulletin 75-04B, as Requested ML19098B2971975-10-28028 October 1975 10/28/1975 Letter Supplemental Information in Technical Specification Change No. 33 2020-01-31
[Table view] Category:Letter
MONTHYEARML24302A1762024-10-22022 October 2024 Core Operating Limits Report Surry 2 Cycle 33 Pattern Hot Revision 0 ML24283A0702024-10-0707 October 2024 Annual Submittal of Technical Specifications Bases Changes Pursuant to Technical Specification 6.4.J IR 05000280/20240102024-10-0202 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000280/2024010 and 05000281/2024010 ML24270A0022024-09-25025 September 2024 Inservice Inspection Owners Activity Report (OAR) ML24248A1712024-09-0303 September 2024 Proposed License Amendment Request - Temporary Service Water Supply to the Component Cooling Heat Exchangers IR 05000280/20240052024-08-26026 August 2024 Updated Inspection Plan for Surry Power Station, Units 1 and 2 (Report 05000280/2024005 and 05000281-2024005), Rev 1 ML24219A2372024-08-23023 August 2024 Issuance of Amendment Nos. 319 and 319, Adoption of TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspection, ML24207A0402024-08-21021 August 2024 Summary of July 17, 2024, Public Meeting - TS 3.7/3.14 AOT for SW Piping Maintenance IR 05000280/20240112024-08-13013 August 2024 Comprehensive Engineering Team Inspection Report 05000280/2024011 and 05000281/2024011 ML24164A0012024-08-12012 August 2024 Proposed Alternative Relief Request V-1 Inservice Testing of Pressure Isolation Valves (EPID l-2023-LLR-0060) IR 05000280/20240022024-08-0101 August 2024 Integrated Inspection Report 05000280/2024002 and 05000281/2024002 05000280/LER-2024-001, Troubleshooting Initiated Unknown Turbine Trip Feature in Control System2024-07-30030 July 2024 Troubleshooting Initiated Unknown Turbine Trip Feature in Control System ML24165A1232024-07-17017 July 2024 Proposed Alternative Relief Request P-1, P-2 Inservice Testing of Residual Heat and Containment Spray Pumps (EPID l-2023-LLR-0058) ML24165A2782024-07-17017 July 2024 Issuance of Amendment Nos. 318 and 318, Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection ML24190A4192024-07-0808 July 2024 Inservice Testing (IST) Program for Pumps and Valves Revised Sixth IST Interval Start Date and Updated Technical Specifications References for Alternative Request V-1 ML24179A2932024-07-0101 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A2422024-06-25025 June 2024 2023 Annual Report of Emergency Core Cooling System (ECCS) Model, Changes Pursuant to the Requirements of 10 CFR 50.46 ML24177A2792024-06-20020 June 2024 Preparation and Scheduling of Operator Licensing Examinations ML24166A0622024-06-18018 June 2024 – Proposed Alternative Relief Request P-3, P-4 Inservice Testing of Boric Acid, Component Cooling Water Pumps ML24157A0542024-06-13013 June 2024 Audit Summary in Support of License Amendment Request for Proposed Reclassification of Low Head Safety Injection Flow Instrumentation Related to Regulatory Guide 1.97 ML24143A1622024-06-12012 June 2024 – Correction to Issuance of Amendment Nos. 297 and 280 and Surry Units 1 and 2, Correction to Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24170B0532024-06-10010 June 2024 DOM-NAF-2-P/NP-A, Revision 0.5, Reactor Core Thermal-Hydraulics Using the VIPRE-D Computer Code IR 05000280/20244032024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2862024-05-22022 May 2024 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000280/2024403 and 05000281- 2024403 ML24141A2512024-05-20020 May 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable - Supplemental Information ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A2302024-05-13013 May 2024 Core 1 Cycle 33 Pattern Mdr Revision 0 ML24130A2032024-05-0909 May 2024 Proposed License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections Supplemental Information ML24130A2492024-05-0909 May 2024 Submittal of Information in Support of Surry Power Station Unit 1 Thermal Shield Flexure Replacement Campaign ML24130A1192024-05-0707 May 2024 Inservice Test Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests - Response to Request for Additional Information Regarding Alternative Request V-1 IR 05000280/20240012024-04-30030 April 2024 Integrated Inspection Report 05000280-2024001 and 05000281-2024001 ML24142A3852024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report ML24122C6522024-04-30030 April 2024 Annual Radiological Environmental Operating Report ML24122B3032024-04-29029 April 2024 Associated Independent Spent Fuel Storage Installation, Revision to Emergency Plan Report of Change IR 05000280/20244022024-04-29029 April 2024 Security Baseline Inspection Report 05000280/2024402 and 05000281/2024402 ML24115A1952024-04-24024 April 2024 Notification of Surry Power Station Comprehensive Engineering Team Inspection - U.S. NRC Inspection Report 05000280/2024011 and 05000281/2024011 ML24054A0142024-04-22022 April 2024 Issuance of Amendment Nos. 297 and 280, and Surry Power Station Unit Nos. 1 and 2, Issuance of Amendment Nos. 317 and 317, to Change Emergency Plan Staff Augmentation Times ML24108A1812024-04-15015 April 2024 Proposed License Amendment Request - Reclassification of Low Head Safety Injection Flow Indication Regulatory Guide 1.97 Variable Supplemental Information ML24095A2172024-04-12012 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report ML24088A2482024-03-26026 March 2024 Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information ML24087A2082024-03-22022 March 2024 Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements ML24078A2642024-03-21021 March 2024 – Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation ML24087A1522024-03-18018 March 2024 Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report ML24023A5762024-03-0808 March 2024 Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center IR 05000280/20230062024-02-28028 February 2024 Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006 ML24032A4712024-02-20020 February 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24051A1782024-02-19019 February 2024 Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML24057A0612024-02-19019 February 2024 And Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage IR 05000280/20230042024-02-0909 February 2024 Integrated Inspection Report 05000280/2023004 and 05000281/2023004 IR 05000280/20244012024-02-0606 February 2024 Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401 2024-09-03
[Table view] |
Text
/ f};_, L' ' *,,,".
,, *_ftl.=tEGULA:.1..m[ DOCKET FILE CO~} .... , ~
VIRGINIA ELECTRIC AlSD POWER COMPANY ~ I RICHMOND, VIRGINIA 23209 50 ... 2 8 0 October 28, 1975
$"'.~~!'
Mr. Bernard C. Rusche Serial No.
Director of Nuclear Reactor Regulation FR/MLB:ell ATTN: Mr. R. W. Reid, Chief.
Operating Reactor Branch 4 U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Rusche:
SUPPLEMENTAL INFORMATION IN SUPPORT OF TECHNICAL SPECIFICATION CHANGE NO. 33 (AMENDMENT TO OPERATING LICENSE DPR-32 AND DPR-37)
SURRY POWER STATION "'" UN ITS* NOS.* 1 AND 2 In response to Mr. M. Dunenfeld's telephone request of October 21; 1975, the appropriate information to verify that core DNB require-ments are satisfied for the Surry Unii 1, Cycle 3 reload is provided in Attachment 1.
Please note that the attached material contains information that is proprietary to the Westinghouse Electric Corporation .. The proprietary inf6rmation has bee~ marked by means of brackets. The basis for marking the material proprietary is identified by marginal notes referrini to the standards in Section 8 of the affidavii of R. A.
Wiesem~nn of record 11 ln the Matter of Accept~nce Criteria for Emergency Core Cooling Systems for Light Water Cooled Nuclear Power Reactor's (Docket No. RM-50-1 )" at transcript pages 3706 through 3710 (February 24, 1972). Due to the proprietary na.ture of this material which was obtained at considerable expense to the Westinghouse Electric Corpora-tion and the release of which would seriously* affect their competitive position, we request this information to be withheld from public dis-closure in accordance with the Rules of Practice, 10 CFR 2.790, and that the information presented therein be safeguarded in accordance with 10 CFR 2.903. We believe that withholding *this information will not adversely affect the public interest.* This inf6rmation is for your internal use only and should not be released to persons or organizations outside the Office of Nuclear Reactor Regulation and the ACRS without prior approval of the Westinghouse Ele~tric Corporation. Should it become necessary to releas~ this information to such persons as part of the review procedure, please contact Westinghouse Electric Corporation, and they will make the necessary arrangem~nts required to protect their proprietary interests.
-1! ;.;-;...,.... ,i-~
tJ ?SI
e vrnorn1A ELEcTmc AND PowER CoMPANY To Mr. Berna rd C.. Rusche Should you have any questionsor comments, we would be most happy to meet with you on this matter at your earliest convenience and well in advance of our pfoposed November 3, 197S restart date for Surry Unit No. 1.
."ZP. >>?. 0/~n~
C. M. Stal 1 ings Vice President-Power Supply and Production Operations Attachment cc: Mr. Norman C. Moseley
/
!1 ::E:
I (I)
I
I ....rt-
- l
,n '
l.C
- r f
0 ll
-~
C V,
.... l (D
~ ~
w 0
£A:
~
IA5
--s (D
Q rt-Q>
1M c,; ~
~
c,,..
~
!!00.0 ~----.:;__-----,~-----------1------------->t-------------*-*----*** 0 q.,
~
w l/1 Ill
<I.
0:
1M .....
0-c-
w 1d e
i" t'.
f*
t:
i m.o ij.,..-.L..-.....t.---<s---JJ.....-..A..-~--.:1--_.A.-_....,_ _
-100.0 il--z..--..a...-_,..!.--.i1o-o--------------
c.o ,,. ....,
\
- 1
~il~l OFFS~T <PERCENT> ]
,*: ; .. -'-~" ~- -*** ... . . ',.. .; . . ...,, .. ' - ~' ........ -*
[suRRY 1 CYCLE* 3 LOWEST CELL AT 118% POWER~t ( q,c.)
' . ~*.:-** -.. ;-: .: .~- \ ,.......
/
u I I I I i
- l::
m
c+
,.~ t'"':__---------------,-------;1!15l---t---------------------:---:--- . : ......
'. ::::i r-~. :
~ lCl
$ii 0 cl\1=' C:
Vl fQ'.i~ ---------*-* ... ----- .
~
,.o r------------------*---~[*:,...,..u--'-------------------
m 1.r
)"'
~--------------------7:1~~.!----------_;-----~----:-~~
~
it~U
~f'i1 ll
,i
~:) }\,
-g
-s m
..,. l{!f,.
~(~
-- c+
PJ
~'\ii - ~
lr,,i 1.6 -
. 1 n......
QJ
~ - i~
Vl D (/)
a.!l
~
,.
+/--____________________ . . . - '
,.~ i"' _:....__ _ _ _ _ _::____;__ _ _ _ _ _ _ _
y*
fi-.
- *i t
~n :j
,., ~
1.55 cosine ~1------------------~----*--* ,- -
t.2 *- 1
. - *f a.1
. * * *
' I * '
,,-'. -~oo.o o.o 1*
~~?~L OFFSET (~ERCEMT) *~
,>* 'el'* * ' " H ~* *
- 0 *-...:., * , . '* * .:. '0
~; > l *-~- * '.' ... " *.,_ .~**, : ** * .. '. *' ' . -~* ~* -... :.. . .... ~ - .~ '. -
"l *"*'
/
DATE:
DOCKET No;**. 50-280/281 oc.tiaber 28, 1975 NOTE TO N.RC AND/OR LOCAL PUBLIC DOCUMENT ROOMS The following ite.m submitted with letter dated October 28, 1975 from -llirgina Electric and Power Company is being withheld from public disclosure, pending review, in accordance with Section 2.790.
PROPRIETARY INFORMATION Core requirements for C~cle 3 reload Regulatory File Room