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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20206B9211999-04-23023 April 1999 Proposed Defueled Tech Specs Stating That Characterization of Revised Review & Audit Function Remain in Plant TS Rather than Be Transferred to Plant QA Plan ML20205N1821999-03-24024 March 1999 Proposed Tech Specs Deleting Condition 2.C(10) from Plant License ML20204D9031999-03-17017 March 1999 Proposed Tech Specs Section 6.2.2,deleting Overtime Restrictions Currently Incorporated in Ynps TS ML20204E5241999-03-17017 March 1999 Revised Tech Specs,Consolidating Mgt Positions & Transferring Review & Audit Functions to Yankee Decommissioning QA Program ML20204E5701999-03-17017 March 1999 Proposed Tech Specs,Removing Section 6.7, Procedures & Programs & Section 6.9, Record Retention, from TS & Transferring to Yankee Decommissioning QA Program ML20155A2561998-10-15015 October 1998 Proposed Defueled Tech Specs Re Required Frequency of Submittal of Radioactive Effluent Release Rept ML20237E3631998-08-20020 August 1998 Proposed Tech Specs,Removing Definition of Site Boundary from Subsection 1.10 of Definitions & Modifying Subsection 5.1 of Design Features ML20197D4341997-12-31031 December 1997 Rev 1 to Ynps License Termination Plan ML20216E2101997-09-0505 September 1997 Proposed Tech Specs,Modifying Defueled TS 3.1.3 to Allow Util to Continue W/Implementation of Ynps Decommissioning Plan Which Has Been Incorporated Into Ynps FSAR ML20141F6391997-05-15015 May 1997 License Termination Plan for Yankee Nuclear Power Station ML20198G6381997-02-0707 February 1997 Rev 12 to Ynps Off-Site Dose Calculation Manual ML20138Q5301996-10-31031 October 1996 Rev 11 to Off-Site Dose Calculation Manual ML20198S6131993-12-31031 December 1993 Partially Deleted Rev 9 to Edcr 93-303, Vessel Internals Segmentation Component Removal Program 1995 ML20198S5681993-08-0202 August 1993 Partially Deleted Rev 6 to Edcr 93-303, Reactor Vessel Internals Segmentation Component Removal Program 1993 ML20126E7601992-12-21021 December 1992 Permanently Defueled Tech Specs ML20058D8451990-10-29029 October 1990 Separate Rept Re Local Leak Rate Test Results from Core 19/20 Refueling Outage ML20058D8421990-06-30030 June 1990 June 1990 Reactor Containment Bldg Integrated Leak Rate Test & Periodic Local Leak Rate Tests ML20055D4031990-06-25025 June 1990 Proposed Tech Specs Re Changes in Safety Injection Tank Min Water Inventory ML20043E6231990-05-31031 May 1990 Proposed Tech Specs 3.10.3 & 3.10.4 Re Limiting Conditions for Operation ML20034B3071990-04-19019 April 1990 Proposed Tech Specs Re HPSI & LPSI Pump Surveillance Frequency ML20042E2211990-04-12012 April 1990 Proposed Tech Specs,Addressing Administrative Changes ML20006A4651990-01-18018 January 1990 Proposed Tech Specs Re HPSI Throttle & Pressurizer Auxiliary Spray Mods & Surveillance Requirements for ECCS ML20005F1431990-01-0505 January 1990 Proposed Tech Specs Re Instrumentation Sys ML19332D1161989-11-22022 November 1989 Proposed Tech Specs Incorporating Wording from Generic Ltr 84-13 Which Removes Table 3.7.4 Re safety-related Mechanical Snubbers ML20247L3581989-09-14014 September 1989 Proposed Tech Specs Re Limiting Condition for Operation & Surveillance Requirements for Control Rod Insertion Limits, Boron Control,Peak LHGR & Xenon Redistribution Multiplier ML20246M0541989-08-31031 August 1989 Proposed Tech Specs,Modifying Pages 3/4 3-19,Table 3.3-4 & 3/4 3-21,Table 4.3-3,to Add Steam Line Monitors & Primary Vent Stack Noble Gas Monitor to Listing of Radiation Monitoring Instrumentation & Surveillance Requirements ML20247M6321989-07-24024 July 1989 Proposed Tech Specs Re Power Distribution Limits ML20246M0221989-07-12012 July 1989 Proposed Tech Spec Tables 3.3-4, Radiation Monitoring Instrumentation & 4.3-3, Radiation Monitoring Instrumentation Surveillance Requirements ML20244D3841989-04-14014 April 1989 Proposed Tech Specs Re Steam Generator Pressure/Temp Limits, Primary Pump Seal Water Sys,Control Room Emergency Air Cleaning Sys & Sealed Source Contamination ML20244D3931989-04-11011 April 1989 Core 20 Startup Program for Yankee Nuclear Power Station ML20246P1401989-03-21021 March 1989 Proposed Tech Specs Adding Snubber DRH-SNB-1 to Table 3.7-4 ML20196B0771988-11-22022 November 1988 Tech Spec Page 3/4 3-2 Inadvertently Omitted from Util 881021 Proposed Change 222 to Tech Specs ML20205L1691988-10-21021 October 1988 Proposed Tech Specs,Removing Description of High Pressurizer Water Level & Modifying Description of Main Coolant Sys High Pressure ML20151Z1871988-08-11011 August 1988 Proposed Tech Spec Changes to Remove Ref to Specific Value of 2,200 Ppm & Provide Generalized Boron Concentration Value & Remove Requirement for Inverse Count Rate Multiplication Measurement After Insertion of Each Five Fuel Assemblies ML20196K7361988-06-27027 June 1988 Proposed Tech Spec Table 3.6.1, Containment Barriers, Deleting Valve VD-V-752 & Tech Spec 3.4.5.1, Main Coolant Leakage Detection Sys, Adding Operability,Action & Surveillance Requirements for Telltale Level Switch ML20196J2831988-06-27027 June 1988 Proposed Tech Specs 3.5.1.e,increasing Nitrogen Supply Pressure to Safety Injection Accumulator to 488 Pounds Per Square Inch Gauge ML20196K1391988-06-27027 June 1988 Proposed Tech Specs Table 3.6-1 ML20150B0371988-06-27027 June 1988 Proposed Tech Specs,Allowing Installation of Two Piping Mods Necessary for Installation of Enhanced Water Cleanup Sys ML20154J5991988-05-19019 May 1988 Proposed Tech Spec 4.9.7.2, Spent Fuel Pit ML20148Q8911988-04-0404 April 1988 Proposed Tech Specs Defining Incore Detection Sys as Combination Sys of Both Fixed & Movable Detectors & Associated Equipment ML20151D0671988-04-0404 April 1988 Proposed Tech Spec Page 3/4 8-10 Re Battery Chargers ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20150E2381988-03-25025 March 1988 Proposed Tech Specs Modifying Containment Isolation Barriers ML20148J2991988-03-25025 March 1988 Proposed Tech Spec Table 3.3-2, ESF Instrumentation & Table 4.3-2, ESF Instrumentation Surveillance Requirements, Reflecting Deleted Modes 5(1) & 5*, Respectively ML20148J2701988-03-23023 March 1988 Proposed Tech Spec 3.1.1.1.2,reflecting Change in Shutdown Margin Switching Temp from 490 to 470 F ML20150C0171988-03-11011 March 1988 Proposed Tech Specs Modifying Section 6.2 & Moving Organization Charts (Figures 6.2-1 & 6.2-2) to Section 501 of FSAR ML20154L9791988-03-0606 March 1988 Rev 6 to Yankee Nuclear Power Station Offsite Dose Calculation Manual ML20148K1671988-01-15015 January 1988 Proposed Tech Specs,Adding Shipping Cask Liners,Vol Reduction Equipment,Shipping Casks Not for Spent Fuel & Spent Fuel Assembly Nondestructive Test Equipment to Tech Spec 3.9.7 ML20149E7271988-01-0505 January 1988 Proposed Tech Spec Figure 6.2.2, Facility Organization, Reflecting Elevated Mgt Concerns Re Security ML20149E8871988-01-0505 January 1988 Proposed Tech Specs,Modifying Tables 3.3-2,3.3-3 & 4.3-2 to Require 18-month Functional Test of First Level Undervoltage Protection for Each of Three 480-volt Emergency Buses 1999-04-23
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20197D4341997-12-31031 December 1997 Rev 1 to Ynps License Termination Plan ML20141F6391997-05-15015 May 1997 License Termination Plan for Yankee Nuclear Power Station ML20198G6381997-02-0707 February 1997 Rev 12 to Ynps Off-Site Dose Calculation Manual ML20138Q5301996-10-31031 October 1996 Rev 11 to Off-Site Dose Calculation Manual ML20198S6131993-12-31031 December 1993 Partially Deleted Rev 9 to Edcr 93-303, Vessel Internals Segmentation Component Removal Program 1995 ML20198S5681993-08-0202 August 1993 Partially Deleted Rev 6 to Edcr 93-303, Reactor Vessel Internals Segmentation Component Removal Program 1993 ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20154L9791988-03-0606 March 1988 Rev 6 to Yankee Nuclear Power Station Offsite Dose Calculation Manual ML20210B5551987-04-20020 April 1987 Rev 4 to Procedure DC-1, Seismic Reevaluation & Retrofit Criteria ML20206D3741987-03-31031 March 1987 Yankee Nuclear Power Station Graded Exercise,Exercise Manual ML20197C0721986-10-20020 October 1986 App E to Inservice Insp Program 80A4721, Valve Testing ML20197C0681986-10-20020 October 1986 App D to Inservice Insp Program 80A4721, Pump Testing ML20212Q6701986-05-19019 May 1986 Draft Procedures Generation Package for Yankee Emergency Response Guidelines ML20134E5451984-12-0303 December 1984 Rev 7 to Engineering Instruction WE-103, Engineering Calculations & Analyses ML20134E5661984-12-0303 December 1984 Rev 0 to Engineering Dept Instruction WE-108, Computer Codes ML20028C3771982-12-16016 December 1982 Public Version of Revised Emergency Plan Implementing Procedures OP-3301 Re Unusual event,OP-3302 Re Alert & OP-3310 Re Evaluation of Radiological Data ML20245H3671982-10-31031 October 1982 RELAP5YA:Computer Program for LWR Sys Thermal-Hydraulic Analysis,Vol 2:Users Manual ML20245H3291982-10-31031 October 1982 RELAP5YA Computer Program for LWR Sys Thermal-Hydraulic Analysis,Vol 1:Code Description ML17341B6731982-10-31031 October 1982 Public Version of Revision 2 to Emergency Plan Implementing Procedure OP-3325, Emergency Equipment Readiness Check. Revision 17 to Table of Contents Encl ML20062B0721982-07-0909 July 1982 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures OP-3301 Re Unusual Event, OP-3302 Re Alert & OP-3303 Re Site Area Emergency.Revised Table of Contents Encl ML20054H8801982-05-26026 May 1982 To RCS Vent Sys Operational Guidelines ML20053E4171982-05-13013 May 1982 Public Version of Notice of Revision in Progress for Revision 3 to Emergency Plan Implementing Procedure OP-3310, Evaluation of Radiological Data ML20042B1241982-03-10010 March 1982 Public Version of Revision 2 to Emergency Plan Implementing Procedure OP-3310, Evaluation of Radiological Data ML20040C0761981-12-30030 December 1981 Public Version of Revised Emergency Plan Implementing Procedure,Including Procedures OP-3303 Re Site Area Emergency & OP-3304 Re General Emergency.Revised Tables of Contents Encl ML20039B8371981-12-0404 December 1981 Public Version of Revision 1 to Emergency Plan Implementing Procedure OP-3344, Security Force Action Under Emergency Conditions. Revision 5 to Table of Contents Encl ML20039A6391981-11-24024 November 1981 Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures OP-3301 Re Unusual Event, OP-3302 Re Alert & OP-3303 Re Site Area Emergency ML20033A2891981-11-0505 November 1981 Public Verison of Revision 1 to Emergency Plan Implementing Procedure OP-3325, Emergency Equipment Readiness Check. Revision 3 to Table of Contents Encl ML20032C5951981-10-29029 October 1981 Core Xv Startup Program ML20031C5471981-10-0202 October 1981 Vol 1 of Inservice Insp Program Plan ML20030C9751981-06-26026 June 1981 Public Version of Change 4 to Emergency Plan Implementing Procedures,Consisting of Table of Contents ML19345A6961976-10-0505 October 1976 Operator Training Program, Procedure AP-0500,Revision 3 ML20148H4381976-01-30030 January 1976 Change 1 to Emergency Procedures 2.50.1,2.50.2,2.50.3, 2.50.13 & 2.50.16,re Local,Site & General Emergency Plans, Environ Sample Collection, & Radiation Emergency Call List, Respectively ML20148G8391975-12-10010 December 1975 Medical Mgt of Radiation Accidents,Plant & Hosp Procedures Manual for Yankee Rowe Nuclear Power Station & North Adams Regional Hosp ML20002A4171972-06-14014 June 1972 Control Rod Surveillance Program:Increased Drop Time Control Rod 19 ML20215F7461958-06-0101 June 1958 Spec for Masonry Work,Floor Tile & Glazed Wall Tile for Yankee Atomic Electric Plant 1997-05-15
[Table view] |
Text
. _ _ _ _. _ _ _ _ _ _ _ _
DOCUMENT NO. 80A4721 lW E 0 1 4
C NUCLEAR ENERGY SERVICES, INC.
I k.
APPENDIX D PUMP TESTING p*$$
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8610310180 861020 PDR ADOCK 05000029 G
PDR FCCM = NES 2C5 2.80
?o g
DOCUMENT NO.
80A4721 NUCLEAR ENERGY SERVICES, INC.
PUMP TESTING Article IWP-1100 of the code states that only pumps that are provided with emergency power are subject to inservice inspection. The only pumps that fall within the scope of IWP are the Low Pressure Safety Injection (LPSI), High Pressure Safety Injection (HPSI) and the Emergency Boiler Feed (EBF) pumps. These pumps are listed in Table D-1.
PUMP LIST NOMENCLATURE g
$*i The following abbreviations have been used in Table D.I.
N Rotative Speed
=
Pi Inlet Pressure
=
Po Outlet Pressure
=
Q Flow Rate s.
=
V Vibration Amplitude
=
Tb Bearing Temperature
=
L Lubricant Level
=
M Monthly
=
X Parameter to be Measured
=
Tne following notes are referenced in Table 0.1.
1.
This is a positive displacement pump, with speed controlled by a governor.
There is no means of determining flow on a monthly basis.
Flow is determined at refueling outages by measuring a level change in the steam generator. This can only be done with the steam generator secondary side manway open, thus it cannot be done at cold shutdown.
2.
Constant speed pump.
3.
There is no means of determining the flow.
FC:V
ct,
~
DOCUMENT NO. 80A4721
" =
NUCLEAR ENERGY SERVICES. INC.
4.
Table IWP-3100-1 specifies that dif ferential pressure shall be one of the test quantities. Yankee Rowe requests relief from the use of differential pressure as a test quantity in favor of our present means of determining adequate pump performance, in accordance with the Technical Specifications. In all cases the suction pressure of the pump is determined by the level of water in a vented tank. The tank levels are controlled by procedures, and the maximum allowable variance in the levels corresponds to a maximum variance in pressure at the pump section of one psi for the LPSI and HPSI pumps, and 4.3 psi for the EBF pump. In all cases the discharge pressure would not be significantly afffected by the maximum variation in suction pressure. being 0.4% for the LPSI pumps,0.196 for the HPSI pumps, and 0.5% for the EBF pump. All values are less than the accuracy of the calibrated pressure guages presently installed.
The Technical Specifications, in recognition of this, require only that minimum volu..aes of water be present, and that minimum values of discharge r
pressure be demon 3t.ated.
4k Yankee intends to maintain the status quo of satisfying the Technical Specifications, and can see no benefit whatsoever of calculating a differential pressure, so long as tank levels and discharge pressures are within their specified limits. If these limits are not met, then discharge pressure will be calculated to ensure adequate pump performance.
&P S
nh' hh FCC'1 z NES 205 2,80
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g TABLE D.1 m
U PUMP LIST to g
Test Measured Parameters 4
System Pump ID P & ID Class Freq. N Pi (4)
Po Q
V T
b z
8 r-f Feedwater (EBF)
P-5 M-14 3
M X
X X
(1)
X X
X s
Safety injection L PSI-1,2,3 M-7 2
M (2)
X X
(3)
X X
X
$a rn Safety injection H PSI-1,2,3 M-7 2
M (2)
X X
(3)
X X
X
@S m
.m 5
P D
/
O
' C3.
O
)
E m
'./,
2 A ', e D
2 j
m
-O y
o
~
g t.
38 rJ Om
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