ML19317G179
| ML19317G179 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/03/1972 |
| From: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Henderson J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19317G178 | List: |
| References | |
| NUDOCS 8002280810 | |
| Download: ML19317G179 (2) | |
See also: IR 05000302/1972002
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UNITED STATES
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ATOMIC ENEK3Y COMMISSION
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REGION 11 - SUITE 818
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230 P E ACHT REE ST REET, NORT HWEST
Tatsewout: 44048848-4503
AT LANY A. GEORGI A 30303
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DIRECTORATE OF REGULATORY vPERATIONS
August 3, '.972
J. B. Henderson, Chief, Reactor Construction Brauch
Directorate of Regulatory Operations, Headquarters
FLORIDA POWER CORPORATION (CRYSTAL RIVER.3), LICENSE NO. CPPR-51, DOCKET
NO. 50-302
The attached report of an inspection of the subject facility on May 9-12,
May 24-26, and June 12, 1972, is forwarded for information. Two items of
noncompliance were discussed in regional office correspondence with the
licensee. One of these was similar to an item previously cited and the
licensee was asked to describe in his answer to o.tr letter, specific
programmatic changes to improve this deficient area. Recently, announced
additions to the quality program staff, organizational changes and added
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emphasis to quality training onsite are expected to cause observable
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improvements in the site quality program.
Over a period, we have had several misunderstandings with FPC concerning
our free access to working level people. As a result of these, the
Region II Director, Test and Startup Branch Chief and the principal
inspector met with FPC management on June 12, 1972. We believe that no
further problems vill be encountered in this area.
The following information is supplied in response to potential generic
issues and specific Headquarters m=moranda:
1.
FPC checks indicated that no Westinghouse DB-50 circuit breakers
are to be used at Crystal River 3 (RT&OB:AR:48).
2.
Valve stems made of h00 series stainless steel are not being used
(Inquiry Report No. 50-269/72-1).
3.
No PECO pattle-type flov switches are to be used (Henderson memoran-
dum dated June 19, 1972).
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No G-E CR-lCo relays vill be used (Inquiry Report No. 50-186/72-3).
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No reduced flov Velan valves will be used (Henderson memorandum dated
March 's, 1972).
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August 3, 1972
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J. B. Henderson
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Only regularly scheduled airline overflights at high altitude have
been observed by site personnel (O'Reilly memorandum dated February 1,
1971).
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Responsible FPC officials agreed to notify Region II of any civil
disturbance incident at the site (O'Reilly memorandum dated
December 15,1970).
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N. C. Moseley, Chief
RO:II:NCM
Reactor Test and Startup Branch
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Enclosure:
RO Rpt. No. 50-302/72-2
(Warnick)
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cc v/ enc 1:
RS, AD For Safety and Security Stds. (3)
L Asst. Director For Boil. Water Reactors (2)
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L Asst. Director For Press. Water Reactors (2)
L Asst. Director For Operating Reactors (3)
L Asst. Director For Site Safety (2)
RO Office of Operations Evaluation
RO Asst. Dir. for Procedures
RO Asst. Dir. for Inspection & Enforcement
RO Files
DR Central Files
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