ML18040A107
| ML18040A107 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/11/1994 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Ridings B AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 9401180050 | |
| Download: ML18040A107 (6) | |
Text
lait itB0I Wp0 r
>>>>*+g Docket No. 50-220 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 January 11, 1994 Ben L. Ridings P.O.
Box 1101
- Kingston, Tennessee 37763
Dear Mr. Ridings:
I am responding to your letter to me dated Decembe 9,
1993.
This lett rovides a written followup to the tele)hone dis ssion between you and er pNr. Bonald S.
- Brinkman, NRC Project Nanager fo~rNine Nile Point Nuclear
- Station, Unit No.
1 (NMP-1) on December 23, i%93, regarding the issues raised in your December 9,
1993, letter.
I apologize to you if you inferred from my November 10, 1993, letter that your comments were invalid or unimportant.
That was not the intent of my letter.
We appreciate efforts to bring safety concerns to our attention, and I assure you that your concerns were seriously considered and thoroughly evaluated by the NRC staff.
The first request in your December 9,
1993, letter was for the address of the NRC's Inspector General (IG).
The IG may be contacted at:
Office of the Inspector General U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Your second request was for a copy of the safety evaluation (SE) for the resolution of the discrepancies regarding the NHP-1 containment isolation valves.
The requested information was provided to you in Attachment 1 to Director's Decision DD-93-10, in Attachment 1 of combined Inspection Report No. 50-220/ 93-01 and 50-410/93-01, and in the SE for License Amendment No.
140 to NHP-1 Facility Operating License DPR-63.
Director's Decision DD-93-10 was provided to you by Dr. Thomas E. Hurley's letter dated May 9, 1993.
Copies of License'mendment No.
140 and combined Inspection Report No. 50-220/93-01 and 50-410/93-01 were provided to you by letter dated November 24, 1993.
With regard to your request for a copy of an SE for upgrading the high pressure coolant injection (HPCI) system into a safety-related
- system, please understand that the NHP-1 HPCI system is not a safety-related system and is not depended upon to satisfy the requirements of 10 CFR 50.46 and 10 CFR Part 50, Appendix K.
This information was previously indicated to you on page ll of DD-93-10, on page 4 of the enclosure to my November 24,
- 1993, letter to you, and on page VII-I of.the NHP-1 Updated Final Safety Analysis Report (UFSAR).
Even though NMP-1 Technical Specification 3. 1.8 requires the 940ii80050 940iii PDR ADOCK 05000220 'l
'@I 1300:3 L SII I~II
J i
Mr. Ben L. Ridings January 11, 1994 operability of the HPCI system, the NMP-1 HPCI system is not safety related.
Therefore, an SE for upgrading the HPCI system into a safety-related system does not exist.
Although the HPCI system is not a safety-related system, it does provide a
highly reliable means for injecting high pressure water for core cooling in the event of a small break loss-of-coolant accident.
Therefore, the NRC staff has included requirements for its operability in the NHP-1 technical specifications.
These requirements are consistent with our philosophy of providing defense in depth against possible accidents.
You also requested copies of the current P&IDs [piping and instrumentation drawings]
and a copy of the current Appendix J procedures.
Copies of the current (Revision ll) UFSAR containment isolation valve tables and the current (License Amendment No.
140) technical specification containment isolation valve tables were provided to you with my November 24, 1993, letter.
The NRC does not maintain copies of licensee's Appendix J procedures or PKIDs; therefore, we are not providing these documents to you.
Copies of your December 9,
1993, letter and of this response have been referred to the NRC's Office of the Inspector General for whatever review and action the IG deems appropriate.
I trust this responds to your concerns.
Sincerely, original signed by:
Steven A. Varga, Director Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Distribution:
'- Docket File+(50-220)
(w/incoming)
NRC 5 Local PDRs (w/incoming)
PDI-1 Reading THurley/FHiraglia, 12/G/18 LJCallan, Acting, 12/G/18 SVarga JCalvo RACapra
- RCooper, Region I
- See revious concurrence DBrinkman CVogan NRR Hail
- Room, 12/G/18
- NOlson, 12/G/18 CNorsworthy CCowgill, Region I OGC
- LNorton, NLN344 (w/incoming)
LA:PDI-1 CVo an PH: PDI-1 OGC*
DBrinkman:smm RWeisman RACa ra JCalvo D:PDI-1 ~
AD*
QJKK SVar h/0 94 rl 94 01 03 94 cl II 93 01 04 94 OFFICIAL RECORD COPY FILENAME: RIDINGS. LTR
0
Mr. 8en L. Ridings January 11, 1994 operability of the HPCI system, the NMP-I HPCI system is not safety related.
Therefore, an SE for upgrading the HPCI system into a safety-related system does not exist.
Although the HPCI system is not a safety-related system, it does provide a
highly reliable means for injecting high pressure water for core cooling in the event of a small break loss-of-coolant accident.
Therefore, the NRC staff has included requirements for its operability in the NMP-I technical specifications.
These requirements are consistent with our philosophy of providing defense in depth against possible accidents.
You also requested copies of the current PSIDs [piping and instrumentation drawings) and a copy of the current Appendix J procedures.
Copies of the current (Revision ll) UFSAR containment isolation valve tables and. the current (License Amendment No.
140) technical specification containment isolation valve tables were provided to you with my November 24, 1993, letter.
The NRC does not maintain copies of licensee's Appendix J procedures or PIIIDs; therefore, we are not providing these documents to you.
Copies of your December 9,
1993, letter and of this response have been referred to the NRC's Office of the Inspector General for whatever review and action the IG deems appropriate.
I trust this responds to your concerns.
Sincerely, A. Va a
Dire even g,
c r
Division of Reactor Pro 'ts - I/II Office of Nuclear Reactor Regulation
0
~ g