ML14192A602
| ML14192A602 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 02/08/1985 |
| From: | Verrelli D NRC Office of Inspection & Enforcement (IE Region II) |
| To: | Utley E Carolina Power & Light Co |
| References | |
| NUDOCS 8503070565 | |
| Download: ML14192A602 (9) | |
Text
FEB.0 8 1985 Carolina Power and Light Company ATTN:
Mr. E. E. Utley Executive Vice President Power Supply and Engineering and Construction 411 Fayetteville Street Raleigh, NC 27602 Gentlemen:
SUBJECT:
DOCKET NO. 50-261 - H. B. ROBINSON STEAM ELECTRIC PLANT EMERGENCY PLAN REVIEW We have completed our review of Revision 6 of H. B. Robinson Steam Electric Plant Emergency Response Plan.
Our review indicates that your H. B. Robinson Steam Electric Plant Emergency Response Plan continues to meet the planning standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.
Please be reminded that 10 CFR 50.47(b) requires NRC approval of any changes to your Plan that may decrease the effectiveness of the Plan.
However, if your safety review indicates no decrease in emergency preparedness, then changes can be made without NRC approval.
In all cases, you should furnish copies of each change to the NRC in accordance with 10 CFR 50.54(q). Also, any changes to the Emergency Plan Implementing Procedures should be made in accordance with the requirements of 10 CFR, Appendix E,Section V (Implementing Procedures).
Should you have any questions regarding this'letter, please contact Mr. W. E. Cline of my staff at 404/221-2665.
Sincerely David M. Verrelli, Chief Reactor Projects Branch 1 Division of Reactor Projects cc:
G. P. Beatty, Jr., Manager R. E. Morgan, Plant General Manager bcc:
State of South Carolina State of North Carolina Resident Inspector Document Control Desk Ru Ru RII RH RI WSartor WCline DCollins rdin P edrickson 2/r)/85 Y2/4 /85 2// /85 2
/85 2/7 /85 8503070565 850208 PDR ADOCK 05000261 F
H. B. ROBINSON SEG PLANT TITLE EMERGENCY RESPONSE PLAN (PLP-oo'i)
REVISION a.+
REV.
APPROVED BY DATE REV.
APPROVED BY DATE REV.
APPROVED BY, DATE 443 6 7_
Recommend By:
DATE Emergency Planning Coordinator Approved By:
DATE Plant General Man ger CONTROLLED COPY.
PAGE TITLE REV.
PROC. NO.
I 9
42 EMERGENCY PLAN 6
PLP-007 Section 4 As assessment of the General Emergency continues, core and containment status, as well as dose projections, will be used to determine follow up protective action recommendations to off-site agencies. EXHIBIT 2.5-3 in PEP-105 contains the criteria necessary to make these determinations.
4.2.2.3 Post-Accident Sampling and Analysis of Reactor and Containment T6 aid in the assessment of core damage, capabilities have been provided to permit sampling for chemical and radioanalysis under a wide range of accident conditions. Using the facilities described in Table 5.7-4, the collection and analysis of samples can be performed without incurring radiation exposures to any individual in excess of 10CFR20.101 limits.
The PASS (Post Accident Sampling System), located outside the Primary Sample Room, is used to collect and analyze Reactor Coolant System, Steam Generator Blowdown and Containment atmosphere samples during post accident conditions. Procedures for obtaining samples of gases and liquids during normal operation (such as a sample of primary coolant) can be safely used during a wide spectrum of accident conditions. During situations involving gross damage to the core, where access to the sampling stations and handling of samples may be limited due to high radiation levels, PASS equipment has been installed and procedures have been developed to minimize the time required to obtain samples and to reduce the radiation levels during transport and analysis of samples.
(See HBR PEP-253, "Collection of Very High Level Radioactive Samples").
sr
H. B.
ROBINSON SEG PLANT TITLE EMERGENCY RESPONSE PLAN (PLP-coy7)
REVISION 4 V
REV.
APPROVED BY DATE REV.
APPROVED BY DATE REV.
APPROVED BY DATE
~
-/
_r-/
Recommend By:
7 DATE Emergency Planning Coordinator Approved By:
DATE Plant General Man ger CONTROLLED COP Al
PAGE TITLE REV.
PROC. NO.
zF42 EMERGENCY PLAN 6
PLP-007 Section 4 As assessment of the General Emergency continues, core and containment status, as well as dose projections, will be used to determine follow up protective action recommendations to off-site agencies.
EXHIBIT 2.5-3 in PEP-105 contains the criteria necessary to make these determinations.
4 4.2.2.3 Post-Accident Sampling and Analysis of Reactor and Containment To aid in the assessment of core damage, capabilities have been provided to permit sampling for chemical and radioanalysis under a wide range of accident conditions. Using the facilities described in Table 5.7-4, the collection and analysis of samples can be performed without incurring radiation exposures to any individual in excess of 10CFR20.101 limits.
The PASS (Post Accident Sampling System), located outside the Primary Sample Room, is used to collect and analyze Reactor Coolant System, Steam Generator Blowdown and Containment atmosphere samples during post accident conditions.
Procedures for obtaining samples of gases and liquids during normal operation (such as a sample of primary coolant) can be safely used during a wide spectrum of accident conditions. During situations involving gross damage to the core, where access to the sampling stations and handling of samples may be limited due to high radiation levels, PASS equipment has been installed and procedures have been developed to minimize the time required to obtain samples and to reduce the radiation levels during transport and analysis of samples.
(See HBR PEP-253, "Collection of Very High Level Radioactive Samples").
sr
H. B.
ROBINSON SEG PLANT TITLE EMERGENCY RESPONSE PLAN (PLP-coi)
REVISION 4-0 REV.
APPROVED BY DATE REV.
APPROVED BY DATE REV.
APPROVED BY DATE 4-17w1r I'
I/~
Recommend By:
r DATE Emergency Planning Coordinator Approved By:
DATE Plant General Man ger CONTROLED COPY
00 PAGE TITLE REV.
PROC. NO.
OF42 EMERGENCY PLAN 6
PLP-0 07 Section4 As assessment of the General Emergency continues, core and containment status, as well as dose projections, will be used to determine follow up protective action recommendations to off-site agencies. EXHIBIT 2.5-3 in PEP-105 contains the criteria necessary to make these determinations.
4.2.2.3 Post-Accident Sampling and Analysis of Reactor and Containment To aid in the assessment of core damage, capabilities have been provided to' permit sampling for chemical and radioanalysis under a wide range of accident conditions. Using the facilities described in Table 5.7-4, the collection and analysis of samples can be performed without incurring radiation expo-sures to any individual in excess of 10CFR20.101 limits.
The PASS (Post Accident Sampling System), located outside the Primary Sample Room, is used to collect and analyze Reactor Coolant System, Steam Generator Blowdown and Containment atmosphere samples during post accident conditions.
Procedures for obtaining samples of gases and liquids during normal operation (such as a sample of primary coolant) can be safely used during a wide spectrum of accident conditions. During situations involving gross damage to the core, where access to the sampling stations and handling of samples may be limited due to high radiation levels, PASS equipment has been installed and procedures have been developed to minimize the time required to obtain samples and to reduce the radiation levels during transport and analysis of samples.
(See HBR PEP-253, "Collection of Very High Level Radioactive Samples").
sr
@61 CP&L Carolina Power & Light Company ROBINSON NUCLEAR PROJECT DEPARTMENT POST OFFICE BOX 790 HARTSVILLE, SOUTH CAROLINA 29550
)
JAN 2 3 1985 Robinson File No:
15505 Serial:
RNPD/85-156 Mr. James P. O'Reilly, Regional Administrator United States Nuclear Regulatory Commission Region II 101 Marietta Street, N. W., Suite 3100 Atlanta, Georgia 30323 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 LICENSE NO.
Dear Mr. O'Reilly:
In accordance with 10CFR50.54(q), Carolina Power & Light Company hereby transmits three copies of recent revisions to the H. B. Robinson Steam Electric Plant Emergency Plan and Procedures.
A list of these revisions is enclosed for your use.
If you have any questions on this subject, please contact our staff.
Very truly yours, R. E. M rgan General Manager H. B. Robinson S. E. Plant RDC:MMS/sr Enclosures cc:
H. E. P. Krug (NRC-HBR) (Enclosure 1)
Document Control Desk (2)
USNRC Washington, D. C. 20555
Enclosure to Serial:
D/85-156
-Page 1 of 1 Revisions to the Emergency Plan and Procedures Procedure Revision Change Effected POM Volume Number Number Pages Vol. 2, Part 5, PLP-007 Rev. 6 Change #10833
- p. 9 of Section 4.0