ML20134D921
| ML20134D921 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 10/06/1996 |
| From: | Blanch P AFFILIATION NOT ASSIGNED |
| To: | Zwolinski J NRC |
| Shared Package | |
| ML20134D719 | List:
|
| References | |
| NUDOCS 9610310094 | |
| Download: ML20134D921 (2) | |
Text
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From:
PAUL M. BLANCH <PMBLANCH91x.netcom.com>
I To:
JZ <JAZWOL9aol.com>
i-Date:-
10/6/96 6:12am
Subject:
Fwd: SONGS LIKE MILLSTONE 7
Subject:
SONGS LIKE MILLSTONE?
r-Sent:
10/6/96 2:44 AM i
. Received:
10/6/96 9:40 AM i
From:
GLEN MILLS, MILLSGLEN9msn.com i
To:-
PAUL BLANCH, PMBLANCH91x.netcom.com CC:
GLEN MILLS, 102502.31259compuserve.com i
Mail: P.O. Box 3393, Mission Viejo, CA 92690 Phone #: 714-768-0585 l'
FAX: 714-458-6455 j
E-Mail: millsglen9msn.com j
October 5, 1996
.The Honorable Shirley Jackson l
Chairperson
. U.S. Nuclear Regulatory Commission l
Washington, D.C. 20555-0001
Dear Chairperson Jackson:
I We have been following closely the developments at Millstone in - particular i
Millstone Unit 2 because it was designed and built by the same NSSS
. vendor i
(Combustion Engineering) and Architect Engineer (Bechtel) as. San =
Onofre Units 2 and 3 (SONGS 2/3) which is only 4 miles from our residential r
j homes - in south San Clemente. We know that the initial design and safety j
analysis for - both Millstone Unit 2 and SONGS 2/3 was done in the early and mid 1970=EDs - by the same management and functional engineering personnel.
Therefore this - leads us to suspect that any nuclear safety concerns at Millstone Unit 2 are - likely to be applicable' to SONGS 2/3. Please confirm that the Nuclear -
Regulatory Commission has evaluated SONGS 2/3 in light of the problems at =
4 Millstone and can assure us the none of the nuclear safety concerns'and l
problems at Millstone exist at SONGS 2/3.
As an example of a nuclear. safety concern at Millstone which maybe -
applicable to SONGS 2/3 consider the following found on the Internet:
l
-ECSteam - generator safety valve'setpoint does not consider piping run. A i
review of the - steam generator design found that the pressure drop between j
the steam - generator and the safety valves was not taken into account in determining the - safety valves-ED setpoint. Thir error was discovered in the analysis for a single MSIV - closure at power. The additional pressure drop could be as high as 100 to 150 - psid. The resulting steam generator pressure would exceed 110% of ASME = design pressure-EE. Other Millstone Unit 2 safety 1
concerns found which maybe - applicable to SONGS.2/3 relate to the spent fuel i
pool, ECCS, LOCA, etc. Please - assure us that none of the Millstone nuclear l
safety concerns and problems exist = at SONGS 2/3. Thank you in advance for your response.
9610310094 961024 1
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l Sincerely, Glen R. Mills Paul M. Blanch Energy Consultant i
135 Hyde Rd.
West Hartford CT 06117 Voice 860-236-0326 Fax 860-232-9350 l
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