Letter Sequence Other |
|---|
|
|
MONTHYEARML19254F2741979-11-0101 November 1979
Requests Extension on Tech Spec Surveillance Interval for Reactor Vessel Internal Vent Valves
Project stage: Other
ML20002D6321981-01-14014 January 1981
Forwards Addl Safety Analysis Justifying Tech Spec Change Request 90,modifying Reactor Vessel Internal Vent Valve Surveillance to Permit Cycle 5 Operation W/O Repeating of Surveillance
Project stage: Other
ML19350A7251981-03-11011 March 1981
Submits Further Justification for Tech Specs Change Request 90 Re Reactor Vessel Internal Vent Valves.Change Requested Mod to Permit Cycle 5 Operation W/O Reperformance of Surveillance
Project stage: Other
ML20215A9291986-09-22022 September 1986
Proposed Tech Specs Making Wording Consistent W/Sts & Extending Waiver on Surveillance of Internal Vent Valves to Cycle 8 Refueling
Project stage: Other
ML20215A9091986-09-22022 September 1986
Application for Proposed Amend 145 to License DPR-54, Revising Tech Specs to Make Wording Consistent W/Sts & to Extend Waiver on Surveillance of Internal Vent Valves to Cycle 8 Refueling.Fee Paid
Project stage: Request
ML20212E4931986-12-17017 December 1986
Smud Vent Valve Matl & Hinge Clearances
Project stage: Other
ML20212E5351987-01-29029 January 1987
Matls-Chemistry Assessment for Internal Vent Valve
Project stage: Other
ML20212E4761987-02-20020 February 1987
Forwards B&W Documents 51-1167259-00, Smud Vent Valves Matl & Hinge Clearances & 51-1167330-00, Matls-Chemistry Assessment for Internal Vent Valves, in Response to G Kalman Request Re Proposed Amend 145 to License DPR-54
Project stage: Other
ML20236V5821987-11-25025 November 1987
Application for Amend to License DPR-54,consisting of Suppl 2 to Rev 2 to Proposed Amend 138,changing Tech Spec Figures 6.2-1 & 6.2-2 to Assign Nuclear Security Manager & Staff Directly to Nuclear Power Production
Project stage: Request
ML20236U3361987-11-25025 November 1987
Proposed Tech Specs Page 1-2b,adding Words to Effect That 3.25 Factor Applicable to Three Consecutive Time Intervals Will Be Reset to Begin After Next Surveillance
Project stage: Other
ML20236U3241987-11-25025 November 1987
Suppl 1 to 860922 Application for Amend to License DPR-54, Consisting of Proposed Amend 145,adding Wording to Tech Spec Page 1-2b Re Surveillance of Internal Vent Valves to Cycle 8 Refueling Outage
Project stage: Request
ML20236V7961987-11-25025 November 1987
Proposed Tech Spec Figures 6.2-1 & 6.2-2,reflecting Util Corporate Support of Nuclear Safety & Nuclear Organization Chart,Respectively
Project stage: Other
ML20237B3961987-12-0707 December 1987
Forwards Amend 92 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Redefine Refueling Interval to Make Definition Consistent W/Sts & Extends Surveillance Interval of Vent Valves to Cycle 8 Refueling
Project stage: Approval
ML20246M1741989-05-0808 May 1989
Submits Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54,per Util 881129 Request to Revise Safety Evaluation.Approval to Extend Refueling Interval as Applies to Reactor Vessel Vent Valve Granted
Project stage: Approval
1986-09-22
[Table View] |
Similar Documents at Crane |
|---|
|
Text
,
9 Metropolitan Edison Company Post Office Box 480
=
Middletown, Pennsylvania 17057 717 9444041 Writer's Direct Dial Number March 11, 1981 Llt 051 Office of Nuclear Reactor Regulation
~$
Attn:
R. W. Reid, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Cournission
~
Washington, D.C.
20555
~
i
Dear Sir:
4-
[;
r.:
e Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Further Justification for TSCR No. 90 Reactor Vessel Internal Vent Valves This letter and attachment are to supply further justification for Technical Specification Change Request No. 90.
This change requested modification of the Reactor Vessel Internal Vent Valve Surveillance to permit Cycle 5 operation withour reperformance of the surveillance. The information noted in the attach- - was discussed in a telephone conversation on February 19, 1981, between Messer
'. Reed and D. Mitchell of my staff, and D. DiIanni and B. Turovlin of the N1..
Sincerely, t
/ @
w D.
ckill Director, TMI-l HDH:DGM:1ma l
l l
Attachment cc:
B. H. Grier.
l B. J. Snyder D. DiIanni l
H. Silver I
L. Barrett 00/
.5 1
l
/ /
l 8108160 %
O h
Metropohtan Edison Company is a Member of the General Pubhc Utilit:es System
e Attachmsnt LlL 051 RCS CHEMISTRY DATA (3-28-79 to present)
DATE ITEM TYPICAL VALUE HIGHEST VALUE SAMPLE TAKEN CRUD
<100 ppb 500 ppb (1) 1-26-81 pH RANGE 5.2 to 5.6 (2)
NA CHLORIDES 50 ppb 500 ppb (2)(3) 6-18-81 BORON LEVEL 2200 to 2300 ppm NA OXYGEN
>300 ppb (2)(6) 1-23-81
>300 ppb (4)(6) 1-24-81 M'ini 15 ppb (4) 1-26-81 Heatup 30 ppb (4) 1-27-81 5 ppb (4)(5) 1-28-81 To 5 ppb (4) 1-29-81 190 F
. CONDUCTIVITY 10 to 15 Micromhos (7)
NA 17 1-23-81 16.8 1-26-81 15 1-27-81
.MKEUP WATER 15 gal / day (8)
NA
' Sources: a) makeup system frou the demineralized water supply which is deaerated and N2 blanketed b)' Reactor Coolant Bleed Tanks (9) c) Borated Water Storage Tank FOOTNOTES.
(1) high crud value found while running reactor coolant pumps for the first time in about 2 years (2) samples taken from Decay Heat Removal System sample line (3) probable analysis probleus.
(4) sample taken from Reactor Coolant Letdown sample point
.(5) hydrazine concentration at.10 ppb
.(6) high value may have. been due to sampling problems / parallel sampling of the pressurizer (hot) indicated 5 ppb (7) all-conductivity samples performed with grab samples, do not have the ability to perform inline test
'(8) makeup value is very conservative on the high side (9) the RCBT are checked 'for pH, chlorides, fisorides, and solids
