ML20037D083
| ML20037D083 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/15/1981 |
| From: | Novarro J LONG ISLAND LIGHTING CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20037D084 | List: |
| References | |
| SNRC-566, NUDOCS 8105210467 | |
| Download: ML20037D083 (4) | |
Text
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LONG ISLAND LIGHTING COMPANY IiMO Jwwww SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTH COUNTRY ROAD + WADING RIVER, N.Y.11792 N,
May 15, 1981 SNRC-56.6.,. A
'N g
j i R
[ h [~.
h EW; 7 [iS$7g Mr. Harold R.
Denton, Director 9"
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Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission A
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Washington, D.C.
20555
,g Shoreham Nuclear Power Station - Unit 1
^
,S' Docket No. 50-322
Dear Mr. Denton:
Forwarded herewith are six (6) copies of LILCO's responses to the Safety Evaluatiori Report (SER) Outstanding Issues listed in Attactuaent 1 Responses to the remaining SER Outstanding Issues, listed in Attachme:4t 2 are scheduled to be submitted on May 27, 1981, unless otherwise noted.
Please note that our response to Outstanding Issue Number 8 "Dyramic Qualification of Seismic Category I Mechanical and Electrical Equipment" has been forwarded to you under separate cover via letter SNRC-561, dated May 15, 1981.
Very t uly yours, f
A'7L%p J. P. Novarro V
Project lianager Shoreham Nuclear Power Station I
RWG:mp Enclosures o
cc:
J.
Higgins
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4 FC-893 5
SNRC-566 ATTACHMENT 1 - SER OUTSTANDING ISSUES Numbar Issue 3
Piping Vibration Test Program - Small Bore Piping / Instrument Lines 5
LOCA Loadings on Reactor Vessel Supports and Internals 13 NUREG-0619, Feedwater Nozzle and Control Rod Return Line Cracking 14 Jet Pump Hold-down Beam 18 NUREG-0313, Rev. 1, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping 22
- Appendix G - Impact Testing 36 Containment Purge System 38
- Fracture Prevention of Containment Pressure Boundary 44 Level Measurement Errors 46 OIE Bulletin 79-27
'l 50 Low and/or Degraded Grid Voltage Condition 51
- Fracture Toughness of Steam Line and Feedwater Line Materials 56 Financial Qualifications (Supplement to SNRC 561 dated April 30, 1981, issue 56) 61 Scram Discharge Volume
- BOP portica of response only 6
6
a..
d ATTACHMENT 2 - SER OUTSTANDING ISSUES SCHEDULED FOR SUBMITTAL ON 5/27/81 (unless otherwise noted)
Number 1
Pool Dynamic Loads 4
Piping Vibration Test Program - Safety related snubbers 6
Downcomer Fatigue Analysis 7
Piping Functional Capability Criteria 9
Environmental Qualification 15 Inservice Testing of Pumps and Valves 16 Leak Testing of Pressure Isolation Valves 17 SRV Surveillance Program 20 Appendix G-IV.A.2.a - Nil Ductility Temperature 21 Appendix G-IV.A.2.c - Pressure-Temperature Limit 23 Appendix G-IV.B - Minimum Upper-Shelf Energy 24 Appendix H-II.C.3.b - Surveillance Capsules 26 Suppression Pool Bypass 27 Steam Condensation Downcomer Lateral Loads 28 Steam Condensation Oscillation and Chugg_ag Loads 29 Quencher Air Clearing. Load 30 Drywell Pressure History 31 Impact Loads on Grating 32 Steam Condensation Submerged Drag Loads 33 Pool Temperature Limit 34 Quencher Arm and Tie-Down Loads 35 Containment Isolation 37 Secondary Containment Bypass Leakage 39 Emergency Procedures 45 Fire Protection 47 Ccntrol System Failures 48 High Energy Line Breaks 53 Emergency Planning (Scheduled for 5/30/81) 55 Q-List 57 TMI-2 Requirements (Third and final submittal scheduled for 5/30/81) 58 Reactor Vessel Materials Toughness 59 Control of Heavy Loads 60 Station Blackout 22*
Appendix G - Impact Testing 38*
Fracture Prevention of Containment Pressure Boundary 51*
Fracture Toughness of Steam Line and Feedwater Materials NSSS portion of response only
These figures are to be included with Outstanding Issue No. 46.
6 b
.