ML17341A519
| ML17341A519 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 09/04/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 8109140279 | |
| Download: ML17341A519 (8) | |
Text
DISTRIBUTION:
Docket File-2 NRC 'PDR L PDR Doc,l:et '5os.
50-250 and 50>>251
Dear Dr. Uhrig:
TERA NSIC ORB01 Rdg DEisenhut SVarga NGrotenhuis CParrish OELD AEOD Dr. Robert E. Uhrig, Vice President Advanced Systems'nd Technology Florida Power and Light Company P. 0.
Box 529100 IIiami, Florida 33152 IE-4 ACRS-10 TLee
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$98>
On August 14, 1980 a conference call was held with representatives of the
- NRC, FPL and Franklin Research Institute regarding the review of the environmental qualification of safety related equipment for the Turkey Point Plant Unit Nos.
3 and 4.
This letter confirms the request for additional information.made in that conference call.
The details of the request are contained in the enc1osure to this letter.
Sincerely, Original signed by:
S. A. Varga Steven A. Varga, Chief Operating Reactors Branch.Pl Division of Licensing
Enclosure:
Request for Additional Information cc w/enclosure:
See next page Bi09140279 Si0'9104 PDR ADOCK 05000250 P
PDR OFFICE/
SURNAMEi OATE $
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1991-399-960
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Robert E. Uhrig Florida Power and Light Company CC:
Nr. Robert Lowenstein, Esquire Lowenstein,
- Newman, Reis and Axelrad 1025 Connecticut Avenue, N.W.
Suite 1214 Washington, D. C.
20036
. Environmental and Urban Affairs Library Florida International University Miami, Florida 33199 Nr. Norman A. Coll, Esquire
- Steel, Hector and Davis 1400 Southeast First National Bank Building Niami, Florida 33131 Nr. Henry Yaeger, Plant Nanager Turkey Point Plant Florida Power and Light Company P. 0.
Box 013100 Ni ami, Fl ori da 33101 Nr. Jack Shreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Resident Inspector Turkey Point Nuclear Generating Station AU. S. Nuclear Regulatory Commission
.Post Office Box 1207 Homestead, Florida 33030
!I A
Encl osure REQUEST FOR ADDITIONAL IHFORtSTION EHVIROHtiEHTAL QUALIFICATION 2.
Please verify that the cable description for the cables in system and component evaluation work (SCEN) sheet 13-28 is the following:
ti-C cross-link polyethylene insulation, neoprene jacket Please provide a correlation of all TtiI action plan equipment items to the specific sections of HUREG-0737 provided in Attachment l. It should be understood that we are requesting identification of all Ttil Action Plan equipment that is installed as of 1/1/81,, correlated to-NUREG-0737 Sections listed in Attachment l. If you have submitted SCEil sheets in
,previous Bulletin 79-01B submittals to the HRC, e.g.,
November of 1980 or July of 1980, identify those SCEM sheets so that this equipment may be reviewed as part of this program.
3.
Please provide the Pyco test report 8770831, Document Reference 861.
Please provide justification for the conclusion that the referenced test reports are applicable to the electrical cables listed in the FPL submittal dated 2/12/81 in response to Bulletin 79-01B Supplement 3.
Please provide the environmental service conditions listed in Attachments 1,
2 5 3 of the original submittal in response to Bulletin 79-018.,
(These are the tempei"ature and pressure profile curves.)
6.
7.
Please provide the normal.environmental service conditions both insid'e the containment and also for high energy line break areas where equipment within scope of this review is located outside of containment.
Please provide the installation dates for the equipment listed on the SCE!l sheets.
ll
. Attachment 1
LIST FOR TtiI-AP ITEllS REOUIRED TO BE IHSTALLED BY 1/1/81 THI-AP Ident.
Humber II. E. 1..2 (p)
II.E.4.2 Function Aux.
FH System Automatic Initi'ation and Flow Indication Containment Isolation Dependability Emergency Power Supply for Pressurizer Heaters (Safety Grade Interfaces)
Emergency Power for Pressurizer Equipment (Safety Grade Interfaces)
II.F.2 (p)
Instrumentation for Detection of Inadequate Core Cooling Anticipatory Reactor Trip upon Turbine Trip II.D.3 II.B.3 II.K.3.9 (u1 II.E.4.1 II.K.2.10 (Baw)
II. K. 3.13 (B)
II.K.3.15 (B)
I I.K. 3'. 19 (B)
II.K.3.21 (B)
II.K.3.27 (B)
Direct Indication of Relief and Safety,.Valve Position Post-Accident Sampling Capability of Reactor Coolant and Containment PID Controller l1odification (If Hardware Change Involved}
Dedi cated Hydrogen Penetrations Safety-Grade Anticipatory Reactor Trip FM 5 Turbine Trip Separation of HPCI and RCIC Initiation Signals Prevention of Spurious Isolation of HPCI and RCIC Sy'stems Interlock on Recirculation Pump Loop (for B'l/Rs)
Restart of Core Spray and LPCI Systems (If Hardware Changed Out)
Provide Common Reference Level for Vessel Level Instrumentation (If Hardware Changed Out)
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