ML18012A291
| ML18012A291 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/28/1996 |
| From: | Robinson W CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18012A293 | List: |
| References | |
| HNP-96-108, NUDOCS 9607090074 | |
| Download: ML18012A291 (201) | |
Text
CATEGORY 1 REGULA Y INFORMATION DISTRIBUTIO SYSTEM (RIDS)
ACCESSION NBR:9607090074 DOC.DATE: 96/06/28 NOTARIZED: NO DOCKET N
&ACIL:50-400 Shearon Harris Nuclear Power" Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION ROBINSON,W.R. Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards rev 27 to Shearon Harris Nuclear Power Plant Emergency Plan including changes to:Min Shift Staffing,ASLB C Commitments, Procedure Consolidation, Miscellaneous Improvements & Clerical/Grammatical categories. A DISTRIBUTION CODE: A045D COPIES RECEIVED:LTR TITLE: OR Submittal: Emergency Preparedness L ENCL j SIZE: I Plans, Implement'g Procedures, 6 C E
NOTES:Application'for permit renewal filed. 05000400 8
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 PD 1 1 LE,N 1 1 INTERNAL FILE CENTER 0 2 2 NRR/DRPM/PERB 1 1 NUDOCS=ABSTR'ACT 1 1 idra.wings EXTERNAL: NOAC 1 1 NRC PDR 1 1
~ g in Ce.shrank II'it~5 D
N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 8 ENCL 8
r 4 t
k
I CÃCM Carolina Power & Light Company William R. Robinson PO Box 165 Vice President New Hill NC 27562 Harris Nuclear Plant JUN 28 'J99~
United States Nuclear Regulatory Commission SERIAL:HNP-96-108 ATTENTION: Document Control Desk 10 CFR 50, Appendix E Washington, DC 20555 I SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 CHANGE TO EMERGENCY PLAN (REVISION 27)
Dear Sir or Madam:
In accordance with 10 CFR 50, Appendix E, Carolina Power 8c Light Company hereby transmits one copy of Revision 27 to the Shearon Harris Nuclear Power Plant Emergency Plan (PLP-201).
This revision replaces all pages of the previous revision.
The changes incorporated by Revision 27 to the Emergency Plan include the following five (5) major categories:
Minimum Shift Staffing
- 2. ASLB Commitments
- 3. Procedure Consolidation
- 4. Miscellaneous Improvements
- 5. Clerical/Grammatical A detailed description of each change is included in Enclosure 1 to this letter. The bases for Categories 2, 3, 4, and 5 are also included in Enclosure 1. Category 1 changes were previously submitted to the NRC for prior approval by letter dated April 2, 1996. The NRC's approval of the proposed changes was documented in a letter dated May 21, 1996.
Each of these changes has been evaluated by the plant staff as not decreasing the effectiveness of the Emergency Plan and have been implemented per 10 CFR 50.54(q).
9607090074 960628 hooch, osoooeoo(I F PDR ~I gp.~/~+5 StaTe Road 1134 New go~~d Hill NC Tel i N G ~A6LWr~.
919 362-2502 Fax 919 362-2095
United States Nuclear Regulatory Commission Page 2 Questions regarding this transmittal may be referred to Mr. T. D. Walt at (919) 362-2711.
Sincerely, MGW Enclosures c: Mr. J. B. Brady Mr. S. D. Ebneter (w/two copies of Emergency Plan)
Mr. N. B. Le (NRR)
I t
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV, 27 Listed below are the "Item Numbers" from the summary of changes, grouped into five (5) major change categories. This is provided to assist in distinguishing the more significant changes to the Harris Emergency Plan from the ClericaVGrammatical changes which have been made. Also provided is an explanation/basis for the changes described in this enclosure.
MINIMUMSHIFT STAFFING 39, 40, 41, 42, 43 ASLB COMMITMENTS 49, 50, 58, 62, 64, 66, 67 PROCEDURE CONSOLIDATION 12, 14, 20, 23, 25, 26, 30, 31, 45, 46, 47, 48, 51, 52, 53, 54, 60, 61, 63, 65, 73, 74 MISCELLANEOUS IMPROVEMENTS 9, 13, 15, 18, 19, 21, 22, 24, 27, 28, 29, 33, 34, 35, 36, 37, 38, 55, 56, 57, 59, 68, 69, 70, 75, 76, 77, 87 CLERICAL/GRAMMATICAL 1, 2, 3, 4, 5, 6, 7, 8, 10, 11, 16, 17, 32, 44, 71, 72, 78, 79, 80, 81, 82, 83, 84, 85, 86, 88, 89, 90 1 of19
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
EXPLANATION/BASIS:
Minimum Shift Staffin The proposed change and justification to minimum shift staffing (Items 39, 40, 41, 42, and 43) was submitted to the NRC for prior approval by Carolina Power & Light (CPS') letter dated April 2, 1996. The staff reviewed the proposed changes and documented their concurrence in a letter dated May 21, 1996. The staff concluded that the proposed change would not reduce the overall effectiveness of the Emergency Plan, and that the staffing changes as proposed would continue to meet the requirements of 10 CFR 50.47(b), Appendix E to 10CFR Part 50 and the applicable guidance in NUREG-0654.
Minimum shift staffing levels, as shown in Table 2.2-1, have been modified to allow the participation of the Mechanical Maintenance, ElectricallIAC and one of the two Radiation Control positions on the Fire Brigade.
Based on the change in "a" above, the designation of Fire Brigade personnel under Emergency positions as "Operations Personnel" was changed to "Plant Personnel" and the asterisk removed from the "5 per FSAR 9.5.1" listed under Minimum Shift Size.'.
Based on the potential addition of three new categories of personnel to the Fire Brigade, the total minimum shift staffing was reduced from 19 to 16.
ASLB Commitments The addition of ASLB Commitments (Items 49, 50, 58, 62, 64, 66, and 67) were analyzed and determined not to be a degradation to the Emergency Plan.
A paragraph was added to Section 4.5.3. to provide information on how the Tone Alert Radio System is activated. The activation is requested by either the State of North Carolina or Wake County, and the actual activation is performed by the National Weather Service.
- b. Steps 5.0.e. and 5.0.f. were added to ensure that the ASLB commitments were maintained.
- c. A statement was added to Section 5.2.5. requiring an annual distribution of an emergency information brochure to school bus drivers and students within the EPZ.
2 of 19
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP'-'201 REV. 27 (continued)
- d. A sentence was added to Step 5.3.1.a.1. requiring the transmission of emergency information from an Emergency Notification Form during monthly drills between the Harris Nuclear Plant (HNP) and the State and County Warning Points.
- e. Section 5.5 was added to include guidance for maintenance and testing of the Public Alerting and Notification System. This consists of the Sirens and Tone Alert Radios.
- f. Section 5.6 was added to include guidance on how oAen to verify the Evacuation Time Estimate. This includes numerical limits and durations of time between verification of adequacy.
Basis: These items fell into two categories:
Items that were already being performed, but not do'cumented in the Emergency Plan:
Maintenance and testing of the Public Notification and Alerting System was added as a responsibility for Emergency Preparedness, and details added in Section 5.5.
The annual distribution of a brochure to school bus drivers and students was added, The transmission of information on an emergency notification form was added to the monthly communication drill between HNP and the State and counties, and Items that were previously unaddressed or needed clarification:
The activation of tone alert radios was clarified by adding a statement referencing activation by the National Weather Service rather than the State/Counties.
Reviewing the Evacuation Time Estimate for adequacy was added as a responsibility of Emergency Preparedness and details added in Section 5.6.
These changes add detail and clarification of ASLB commitments to the Emergency Plan.
As such, they are enhancements and have no potential for adversely impacting the Plan.
Procedure Consolidation The consolidation of 48 Plant Emergency Procedures (PEPs), 6 Emergency Performance Tests (APTs) and 1 Administrative Procedure (AP) into 15 "new" PEPs (Items 12, 14, 20, 23, 25, 26, 30, 31, 45, 46, 47, 48, 51, 52, 53, 54, 60, 61, 63, 65, 73, and 74) was analyzed and determined not to be a degradation to the Emergency Plan.
Basis: The procedures were grouped by category or location of usage (for example, Technical Support Center (TSC), Notification and Communications, and so forth), rather than by each individual position in a facility or type of communication. This results in less switching back and forth between procedures and eases the potential for confusion.
3 of19
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Miscellaneous Im rovements The various miscellaneous improvements (Items 9, 13, 15, 18, 19, 21, 22, 24, 27, 28, 29, 33, 34, 35, 36, 37, 38, 55, 56, 57, 59, 68, 69, 70, 75, 76, 77, and 87) were analyzed and determined not to be a degradation to the Emergency Plan.
Basis: This grouping includes a wide variety of modifications that have a minor improvement impact on the Emergency Plan. These were considered minor improvements that either increased the accuracy of a given statement, or updated items to reflect changes in plant policy. Examples are as follows:
- a. Four additional family care facilities were added to Fig.1.8-2. This list is updated periodically by checking with the surrounding counties.
- b. The designees for the Superintendent -'hift Operations was previously addressed in "old" procedure PEP-102. Since this is already addressed in operations
'procedure OMM-001 it was felt to be an unnecessary redundancy and deleted.
The supervisory responsibilities of the Technical Analysis Director were expanded to more accurately reflect the existing Emergency Response Organization (ERO).
d.'he requirement for the Radiological Control Coordinator to establish temporary locations for the distribution of emergency dosimetry was deleted since these locations are already established in the emergency facilities.
- e. The supervisory responsibilities of the Communications Director were expanded to more accurately reflect the existing ERO.
The requirement for the Status Board Plotters in the TSC to post data on the various sheets that used to be posted around the TSC was deleted. The primary method of displaying such data is on the three projection screens installed during recent renovations to the facility.
The supervisory responsibilities of the Communications Manager were expanded to more accurately reflect the existing ERO.
E The requirement for the Status Board Plotters in the Emergency Operations Facility (EOF) to post data on the various sheets that used to be posted around the EOF was deleted. The primary method of displaying such data is on the three projection screens installed during recent renovations to the facility.
The requirement for the News Coordinator to coordinate the release of news information with the Company Spokesperson was changed to coordinating the 4 of 19
Y l1
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued) information with the Joint Information Center (JIC) Director. This more accurately matches the functions of the JIC Director rather than the Company Spokesperson.
The first two responsibilities of the Technical Analysis Manager (TAM), assess the cause of the emergency and provide technical support in various areas, were rewritten. Those types of analysis are more properly focused on the Technical Analysis Director (TAD) and the Accident Assessment Team (AAT). The two steps were replaced with requirements that are more closely aligned with the responsibilities of the EOF, namely providing information for off-site organizations.
- k. This responsibility for the TAM to analyze the emergency for its potential impact on other nuclear facilities was deleted since it was felt to be inappropriate for the scope of the position's responsibilities during a declared event. Such an analysis would be more appropriate as a follow up action after cessation of the event.
This responsibility for the TAM to develop oF-normal procedures was deleted since such a responsibility more properly belongs with the TAD and AAT.
- m. The supervisory responsibilities of the Admin and Logistics Manager (ALM)were expanded to more accurately reflect the existing ERO.
- n. The requirement for the ALMto handle the processing of payroll and other such expenditures was deleted since this function would continue to be performed by corporate personnel.
- o. A description of the Emergency Preparedness position in the EOF was added to provide a basis for the responsibilities of the position.
The requirement for the Supervisor - Emergency Preparedness to sign Annex A was deleted since there was no basis for his signing this item in the Emergency Plan. The supervisor's annual review and approval of these agreements will be documented outside the E-Plan and kept on file by HNP Emergency Preparedness (EP).
- q. Five items were added to Annex A to document the agreements of the State of NC and the four EPZ counties to contact HNP ifthey experienced any problems with the transmitters used to set ofF the sirens in their counties.
- r. (See "p" above) The signature block for the Supervisor - Emergency Preparedness was removed and a statement referencing a review of the agreements being kept on file by HNP EP added.
5 of19
0 1
1 I ill II I
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Annex G, Sect. 2.0, previously described the Emergency Operations Facility (EOF) as ifit were an organization external to the site. Since the EOF is an integral part of the HNP Emergency Response Organization and staffed by HNP personnel, this section was deleted.
ClericaVGrammatical The remaining clericaVgrammatical changes (Items 1, 2, 3, 4, 5, 6, 7, 8, 10, 11, 16, 17, 32, 44, 71, 72, 78, 79, 80, 81, 82, 83, 84, 85, 86, 88, 89, and 90) were analyzed and determined not to be a degradation to the Emergency Plan.
6 of 19
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. P~ae ~Chan e Pages 2-8 Page numbers listed in the Table'of Contents were adjusted as necessary.
Page 2, TOC, Sect. 1.2 "...Plan and Procedures" was changed to
"...Plan and Implementing Procedures" as a more accurate statement.
Page 3, TOC, Sect. 2.4.10.6 "Emergency Preparedness Advisor" was inserted as a new section.
Page 5, Sects. 5.5 and 5.6 New Sections Page 9, Sect. 1.2, 1st para. "...and Plant Emergency Procedures (PEPs) is..." was changed to "...and Implementing Procedures (Plant Emergency Procedures and Emergency Phone List) are..." as a more accurate statement.
Page 9, Sect. 1.2, 1st para. "The HNP E-Plan and Procedures..." was changed to "The HNP E-Plan and Implementing Procedures...".
Page 10, Sect. 1.2, 3rd para. This is a new statement added to reference the Emergency Phone List.
Page 10, Sect. 1.2, 4th para. "A list of PEPs required..." was changed to "A list of procedures..." as a more accurate statement since the list contains more than just PEPs.
Page 18, Fig. 1.8-2 Items 17-21 were added to the drawing and to the list beneath the drawing. A NOTE was also added since the "list" is static and subject to change.
'0 Page 20, Table 1.8-2 The "degree" symbols were repositioned to correct a typo.
7 of 19
p t
i
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. ~Pa e ~Chan e Page 20, Sect. 2.4, 1st para. "...through 2.4.10.5." was changed to
"...through 2.4.10.6." since a new section was added.
12 Page 23, Step 2.4.a. "...in accordance with PEP-407..." was changed to "..".in accordance with PEP-400..." as part of the procedure consolidation project.
13 Page 24, Sect. 2.4.2, 1st para. "...in accordance with PEP-102." was changed to "...in accordance with operations procedures." Designees for the Superintendent-Shift Operations are addressed in POM procedure OMM-001 since this is a potential occurrence during normal plant operations as well as during a declared emergency.
Page 24, Sect. 2.4.2, 1st para. "...in accordance with PEP-407." was changed to "...in accordance with PEP-400."
as part of the procedure consolidation project.
15 Page 26, Step 2.4.3.1.a. "Supervise the Accident Assessment Team."
was changed to "Supervise the Accident Assessment Team, TSC ERFIS Operator and TSC Computer Support." as a more accurate description.
16 Page 29, Step 2.4.5.i. "Generate periodic listings..." was changed to "Generate listings, as needed,..." as a clerical change of minor impact.
17 Page 29, Step 2.4.5.k. This Step was rewritten without changing the intent. This requires the Security Director to notify personnel within the EAB of the declaration of a Site or General Emergency.
8 of19
P ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. ~Pa e ~Chan e 18 Page 31, Step 2.4.6.7.f. "Establish temporary dosimetry issue areas where necessary." was deleted as unnecessary since there are numerous established dosimetry issue, areas for normal, and emergency operations.
19 Page 32, Sect, 2.4.7.2., 1st para. "...two, Status Board Plotters and the Admin Team." was changed to "...two Status Board Plotters, the TSC Logkeeper and the Admin Team." as a more accurate description.
20 Page 33, Step 2.4.7.2.a. "...as per PEP-301,..." was changed to "...as per PEP-310,..." as part of the procedure consolidation project.
21 Page 33, Step 2.4.7.2.c. "...located in the TSC." was changed to
"...located in the TSC, as needed." since the majority of the TSC Status Boards are now used as a backup method of displaying data.
22 Page 33, Sect. 2.4.7.3., 1st para. "...Emergency Communicator-Corp Comm/JIC and two Status Board Plotters."
was changed to "...Emergency Communicator-Corp Comm/JIC, Representatives to the State and County EOCs and two Status Board Plotters." as a more accurate statement.
23 Page 33, Step 2.4.7.3.a. "...as per PEP-301,..." was changed to "...as per PEP-310,..." as part of the procedure consolidation project.
24, Page 33, Step 2.4.7.3.b. "...on status boards in the EOF." was changed to "...on status boards in the EOF, as needed." since the majority of the EOF Status Boards are now used as a backup method of displaying data.
9 of19
V F
N 1
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. ~Pa e ~Chan e 25 Page 33, Step 2.4.7.3.e. "...as per PEP-301." was changed to "...as per PEP-310." as part of the procedure consolidation project.
26 Page 33, Sect. 2.4.8., 1st para. "...in accordance with PEP-407." was changed to "...in accordance with PEP-400."
as part of the procedure consolidation project.
27 Page 35, Step 2.4.8.5.d. "...with the Company Spokesperson." was changed to "...with the JIC Director." as a more accurate statement.
28 Page 35, Step 2.4.8.5.e. "Transmitting approved COL news releases to Corporate Communications." was changed to "Coordinating the distribution of approved CPS'ews releases with an Administrative Coordinator." as a more accurate statement of responsibilities.
29 Page 35, Step 2.4.8.6.a. "Ensuring that the JIC staff is provided..."
was changed to "Ensuring that the Public Information Specialists are provided..." as a more accurate statement.
30 Page 35, Sect. 2.4.9., 1st para. "...in accordance with PEP-407." was changed to "...in accordance with PEP-400."
as part of the procedure consolidation project.
31 Page 36, Sect. 2.4.10. "...in accordance with PEP-407." was changed to "...in accordance with PEP-400."
as part of the procedure consolidation project.
32 Page 38, Step 2.4.10.3.3.c. "Collect and evaluate..." was changed to "Ensure the collection and evaluation of..."
as a more accurate statement of responsibilities.
10 of 19
I t
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. P~ae ~Chan e 33 Page 39, Step 2.4.10.4.a and b. These steps were completely rewritten to more accurately reflect responsibilities.
34 Page 39, Step 2.4.10.4.e. This step was deleted since the expectation that the TAMwould analyze an emergency situation for its,impact on other nuclear plants was unrealistic. This. function would more likely be performed aAer the end of a declared emergency.
35 Page 39, Step 2.4.10.4.g. This step was deleted since the development of out-of-normal operating and emergency procedures would be performed on site by the TAD and AAT.
36 Page 39, Sect. 2.4.10.5., 1st para. "...activities of the Administrative Team Leader and Administrative Team." was changed to "...activities of the Administrative Team Leader and Admin Building Assembly Area Leader." as a more accurate statement of responsibilities.
37 Page 40, Step 2.4.10.5.d. This step was deleted since payroll concerns would be a corporate function as a normal part of company business even during a declared emergency.
38 Page 40, Sect. 2.4.10.6. A description of the Emergency Preparedness position in the EOF was added and "Advisor" added to the title.
NOTE: The following changes to Table 2.2-1, listed in Items 39 - 43 have already been pre-approved by the NRC.
39 Page 42, Table 2.2-1, Item 5 "Mechanical Maintenance 1 ElectricaVI&C Maintenance 1" was changed to "Mechanical Maintenance 1*
ElectricaVIAC Maintenance 1*"
11 of 19
e ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. P~ae ~Chan e 40 Page 42, Table 2.2-1, Item 6 "Radiation Control Personnel" was changed to "Radiation Control Personnel 41 Page 42, Table 2.2-1, Item 8 "Operations Personnel 5* per FSAR 9.5.1."
was changed to "Plant Personnel 5 per FSAR 9.5.1."
42 Page 42, Table 2.2-1', end of table "CPAL TOTAL (Less Security) 19" was changed to "CP&L TOTAL (Less Security) 16" 43 Page 42, Table 2.2-1, NOTE "May be provided by shift personnel who are also assigned other functions." was changed to "May also be assigned to Fire Brigade positions."
44 Page 44, Fig 2.4-1 The position of "Emergency Preparedness" was changed to "Emergency Preparedness Advisor" as a title change.
45 Page 54, Sect. 3.9.4. "...listed in RTM-92 and PEP-362." was changed to "...listed in RTM-92 and PEP-340." as part of the procedure consolidation project.
46 Page 58, Step 4.2.a. "...is contained in PEP-301..." was changed to "...is contained in PEP-310..." as part of the procedure consolidation project.
47 Page 60, Step 4.5.1.a. "...as implemented by PEP-104," was changed to "...as implemented by PEP-110."
as part of the procedure consolidation project.
12 of 19
S V Iff
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. P~ae ~Chan e 48 Page 61, Sect. 4.5.2.,4th para. "...contained in PEP-104." was changed to
"...contained in PEP-110." as part of the procedure consolidation project.
49 Page 62, Sect. 4.5.3., 1st para. "Activation of the sirens and tone alert radios..." was changed to "Activation of the sirens...". A second paragraph was added to this Section to address activation of the tone alert radios. The last sentence of the 1st paragraph was moved and became the last sentence of the 2nd paragraph.
50 Page 62, Sect. 4.5.3., 2nd para. This paragraph was added and details activation of the tone alert radios. This was added as part of the E-Plan ASLB commitment update.
51 Page 62, Sect. 4.6.2., 1st para. "Plant Emergency Procedure PEP-382, Personnel Accountability, describes..." was changed to "PEP-350 describes..." as a simplification and as part of the procedure consolidation project.
52 Page 62, Sect. 4.6.2., 2nd para. "...in accordance with plant emergency procedure PEP-381..." was changed to "...in accordance with PEP-350..." as a simplification and as part of the procedure consolidation project.
53 Page 63, Sect. 4.6.3.2. "...in accordance with PEP-371." was changed to "..in accordance with PEP-330."
as part of the procedure consolidation project.
54 Page 65, Sect. 4.6.3.4., 9th para. "...contained in PEP-371." was changed to
"...contained in PEP-330." as part of the procedure consolidation project.
13 of 19
~x I
f
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No, P~ae ~Chan e 55 Page 67, Step 4.6.3.7.1., 2nd para. "...members of the public in Wake County."
was changed to "...members of the public."
since the facilities in question would serve the "public" not just citizens of Wake County.
56 Page 77, Table 4.6-1, Item B.2 "<100 net cpm py with HP210 probe or equivalent sensitivity" was changed to "No detectable py above background" based on a change in plant procedures.
57 Page 77, Table 4.6-1, Item B.4 "High Contamination" was deleted as a contamination limit since the use of the term has been deleted from plant Health Physics procedures.
58 Page 80, Steps 5,0.e. and f. These were added as new requirements.
59 Page 81, Sect. 5.1.4. "A list of Plant Emergency Procedures..."
was changed to "A list of procedures..." as a more accurate statement.
60 Page 82, Sect. 5.2.1., 1st para. "...are contained in PEP-403..." was changed to "...are contained in PEP-400..." as part of the procedure consolidation project.
61 Page 82, Sect. 5.2.1., 3rd para. "...as defined in PEP-407..." was changed to
"...as defined in PEP-400..." as part of the procedure consolidation project.
62 Page 83, Sect. 5.2.5., 2nd para. "(2)annual distribution of a school brochure to school bus drivers and students" was added as part of the ASLB E-Plan update.
63 Page 84, Sect. 5.3.1., 1st para. "Emergency Plan Implementation Procedure PEP-406..." was changed to "PEP-400..." as a simplification and as part of the procedure consolidation project.
14 of 19
0 i
'I 4
'I II II
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. P~ae ~Chan e 64 Page 84, Step 5.3.1.a.l. "This shall include the transmittal of the information on an Emergency Notification Form." was added to the end of the Step as part of the ASLB E-Plan update.
Page 85, Sect. 5.3.2., 1st para. "...are described in the Plant Emergency Procedure PEP-406." was changed to "...are described in PEP-400." as a simplification and as part of the procedure consolidation project.
66 Page 87, Sect. 5.5 This new section was added to provide an overview of the testing and maintenance of the Public Alerting and Notification Systems.
~
This was added as part of the E-Plan ASLB commitment update.
67 Page 88, Sect. 5.6 This new section was added to describe requirements for Evacuation Time Estimate.
This was added as part of the E-Plan ASLB commitment update.
68 Page 98, Annex A, 1st para. "Agreements with the original letters and reconfirmations of the agreements are on file in the HNP EP office." was changed to "Copies of the original agreements are kept on file by HNP Emergency Preparedness." as a more accurate statement.
69 Page 98, Annex A, Table Items 13-17 were added as new agreements.
70 Page 98, Annex A, 2nd para (after table) This statement was rewritten and the signature block removed as unnecessary.
71 Page 116, Annex D, Item J.10.b. "Fig 1.8-1" was added as a reference.
72 Page 118, Annex D, Item P.8 "pgs. I and ii" was changed to "pgs. 2-8" to correct a typo.
15 of 19
0 I
5
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. ~Pa e ~Chan e 73 Page 119, Annex E This listing of implementing procedures was completely rewritten to reflect changes made during the procedure consolidation project.
74 Page 120, Annex F "...as a form in PEP-301, 'Notification of NON-CPEcL Emergency Response Organizations.'" was changed to "...as a form in PEP-310, 'Notifications and Communications.'" as part of the procedure consolidation project.
75 Page 121, Annex G, Sect. 2.0 This was deleted as unnecessary since the EOF is an integral part of the Emergency Response Organization and this Emergency Plan.
76 Page 121, Annex G, Sect. 3.3 "...coordinates the activities in the State Emergency Response Team (SERT)
Headquarters and the..." was changed to
"...coordinates the activities of the State Emergency Response Team (SERT) at the..." as a more accurate statement.
"Personnel within the SERT Headquarters and the SEOC will confer..." was changed to "Personnel within the SEOC..." as a more accurate statement.
77 Page 122, Annex G, Sect. 3.5 The "old" first paragraph was deleted as redundant.
78 Page 122, Annex G, Sect. 3.5, 2nd para. "The Chatham County Department of Emergency Operations..." was changed to "The Chatham County Emergency Management Agency..." as a title change.
16 of 19
'I
~ ~-
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. ~Pa e ~Chan e 79 Page 122, Annex G, Sect. 3.6 "The Harnett County Emergency Management Agency has the..." was changed to "The Harnett County Emergency Services Agency has the..." as a title change.
80 Page 123, Annex G, Sect. 3.8, Title "Sanford-Lee Count Emer enc Mana ement A enc "was changed to "Sanford-Lee Count Emer enc Services
~Aenc "as a title change.
81 Page 123, Annex G, Sect. 3.8 "The Sanford-Lee County Emergency Management Agency" was changed to "The Sanford-Lee County Emergency Services Agency" as a title change.
82 Page 123, Annex G, Sect. 3.8, 1st Star "...the Sanford-Lee County's Radiological Emergency Plan..." was changed to "...the Lee County Plan..." as a title change.
83 Page 123, Annex G, Sect. 3.8, 3rd Star "...by the Sanford-Lee County Plan..." was changed to "...by the Lee County Plan..." as a title change.
84 Page 123, Annex G, Sect. 3.10, Title "Wake Count Emer enc Mana ement
~A" h gd *'
Ma'or Res onse/Lo istics Services Division" as a title change.
85 Page 123, Annex G, Sect. 3.10 "The Wake County Emergency Management Agency" was changed to "The Wake County Major Response/Logistics Services Division" as a title change.
17 of 19
t 1
'I I
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. P~ae ~Chan e 86 Page 124, Sect. 5.0 "...Daniel Construction, and Ebasco..." was changed to "...Becon Construction, and Raytheon Engineers..." as an update of standing contracts held by HNP.
"...maintained with the Babcock Ec Wilcox Company..." was changed to "...maintained with Framatome Technologies..." as an update of standing contracts held by HNP.
87 Page 127, Table G. 1-1, Item 2 This item was deleted since the EOF is an integral part of the HNP Emergency Response Organization.
88 Page 127, Table G. 1-1, Item 9 Under "Agent for Initial Notification" the location "Communications Center" was changed to "Sanford Municipal Center"as a more accurate description of the location.
89 Page 129, Fig. G-1 "Harnett County Emergency Management Agency" was changed to "Harnett County Emergency Services Agency" as a title change.
"Sanford-Lee County Emergency Management Agency" was changed to "Sanford-Lee County Emergency Services Agency" as a title change.
"Wake County Emergency Management Agency" was changed to "Wake County Major Response/Logistics Support Agency" as a title change.
18 of 19
~ ~
pI
ENCLOSURE 1 TO HNP-96-108
SUMMARY
OF CHANGES IN PLP-201 REV. 27 (continued)
Item No. ~Pa e .~Chan e 90 Page 131, Fig. G-3 "Harnett County Emergency Management Agency" was changed to "Harnett County Emergency Services Agency" as a title change.
"Sanford-Lee County Emergency Management Agency" was changed to "Sanford-Lee County Emergency Services Agency" as a title change.
"Wake County Emergency Management Agency" was changed to "Wake County Major Response/Logistics Support Agency" as a title change.
19 of 19
0, g"l CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PLANT OPERATING MANUAL VOLUME 1 PART 2 PROCEDURE TYPE: Plant P gram NUMBER: PLP-201 TITLE: Emergency Plan REVISIO 6 PLP-201 Rev. 26 Page 1 of 131
/
Table of Contents Title Pacae List of Tables 7 List of Figures 8
1.0 INTRODUCTION
. . . . . . . . . ~
1.1 Authority/Requirements 1.2 Purpose of HNP Emergency Plan and Procedures 1.3 Responsibility for Plan Development and Review 10 1.4 Emergency Classes 10 1.5 Plant Site Description 1.6 Plume Exposure Emergency Planning Zone (EPZ) 1.7 Ingestion Exposure Emergency Planning Zone 1.8 Demographic Information 12 1.9 Supporting Emergency Plans 12
- 1. 10 FSAR Commitment Cross-Reference 12 2.0 ORGANIZATION AND RESPONSIBILITIES 21 2.1 General 21 2.2 Emergency Organization 21 2.2.1 Corporate Emergency Organization 21 2.2.2 On-Site Emergency Response Organization 21 2.3 Command and Control 22 2.4 Assignment of Responsibilities 23 2.4.1 Superintendent Shift Operations 23 2.4.2 Site Emergency Coordinator 2.4.3 Plant Operations Director 25 2.4.3.1 Technical Analysis Director 26 2.4.3.2 Accident Assessment Team 26
- 2. 4. 3. 3 Fire Brigade Team Leader 26 2.4.3.4 Fire Brigade 27
- 2. 4. 3. 5 First Aid Team 27 2.4.3.6 Operations Leader 27 2.4.4 Emergency Repair Director 27 2.4.4.1 Damage Control Coordinator 28 2.4.4.2 Damage Control Team Leaders 28 2.4.4.3 Damage Control Teams 28 2.4.4.4 Deleted 29 2.4.4.5 Maintenance Planners 29 2.4.4.6 OSC Storekeeper 29 Security Director 29 2.4.5 ' Admin Building Assembly Area Leader 30 2.4.6 Radiological Control Director 30 PLP-201 Rev. 26 Page 2 of 131
Table of Contents (continued)
Title Pacae 2.4.6.1-2.4.6.4 Deleted 30 2.4.6.5 Chemistry Coordinator 31 2.4.6.6 Chemistry Team . 31 2.4.6.7 Radiological Control Coordinator 31 2.4.6.8 Radiological Control Teams 32 2.4.7 Emergency Communicators 32 2.4.7.1 Emergency Communicator - Control Room 32 2.4.7.2 Communications Director 32 2.4.7.3 Communications Manager 33 2.4.8 Joint Information Center Staff 33 2.4.8. 1 Company Spokesperson 34 2.4.8.2 JZC Director 34 2.4.8.3 Company Technical spokesperson 34 2.4.8.4 Administrative Coordinator 2.4.8.5 News Coordinator 35 2.4.8.6 Public,Znformation Coordinator 35 2.4.9 Representatives to the State/County Emergency Operations Centers 35 2.4.10 Emergency Response Manager and Staff 36 2.4.10.1 Emergency Response Manager 36 2.4.10.2 Deleted 37 2.4.10.3 Radiological Control Manager 37 2.4.10.3.1 Technical Advisor 37 2.4.10.3.2 Dose Projection Team Leader 38 2.4.10.3.3 Environmental Field Coordinator 38 2.4.10.3.4 Environmental Monitoring Teams 38'9 2.4.10.3.5 Dose Projection Team 2.4.10.4 Technical Analysis Manager 39 2.4.10.5 Administrative and Logistics Manager 39 2.4.10.6 Deleted 40 2.4.10.7 Deleted 40 2.5 Outside Organization Support ~ ~ 40 3 0 EMERGENCY FACILITIES'OMMUNICATIONS~ AND EQUIPMENT 3.1 General 3.2 Main Control Room (MCR) 3.3 Technical Support Center (TSC) 46 3.4 Operational Support Center (OSC) 48 3.5 Emergency Operations Facility (EOF) 48 3.6 Joint Information Center (JIC) 49 PLP-201 Rev. 26 Page 3 of 131
Table of Contents (continued)
Title Pacae 3.7 Non-CP&L Facilities 50 3.8 Communications Systems 51 3.9 Assessment Equipment 52 3.9.1 Emergency Response Facilities Information System (ERFIS) and Safety Parameter Display System (SPDS) 52 3.9.2 Seismic and Hydrological Data 53 3.9.3 ~
Radiological Monitoring 53 3.9.4 Normal and Post Accident Sampling System (PASS) 3.9.5 Meteorological Instrumentation 3.9.6 Field Monitoring Equipment 55 3.9.7 Laboratory Facilities 55 4.0 EMERGENCY MEASURES AND OPERATIONS 57 Emergency Classification 57 4.2 Notification 58 4.3 Activation 58 Assessment Actions 59 4.4.1 Evaluation of Plant Conditions 59 4.4.2 Plant Radiological Monitoring 59 4.4.3 Dose Projection 59 4.4.4 Environmental Monitoring 60 Protective Actions for the Public 60 4.5.1 Protective Action Guides 60 4.5.2 CP&L Recommendations to Local Authorities 61 4.5.3 Public Alerting, Warning, and Notification 61 4.6 Protective Actions for On-Site Personnel 4.6.1 On-Site Alerting, Warning, and Notification 4.6.2 Evacuation and Personnel Accountability 62 4.6.3 Radiological Exposure Control 63 4.6.3.1 Radiological and Contamination Control Facilities 63 4.6.3.2 Exposure Records for Emergency Workers 63 4.6.3.3 Use of Protective Equipment and Supplies 63 4.6.3.4 Emergency Worker Exposures During Lifesaving and Repair/Reentry Efforts 4.6.3.5 Deleted 65 4.6.3.6 Decontamination and First Aid 65 4.6.3.6.1 Treatment of Injured and Contaminated Persons 4.6.3.6.2 Initial First Aid 65
- 4. 6. 3. 6. 3 Decontamination 66 4.6.3.6.4 Medical Transportation 66 4.6.3.7 Medical Treatment 67 PLP-201 Rev. 26 Page 4 of 131
Table of Contents (continued)
Title Pacae 4.6.3.7.1 Hospital Facilities . . . . . . . . . . . . . . . . 67 4.6.3.7.2 Medical Consultants 4.6.3.8 Contamination Control of Drinking Water and Food 68 4.7 Fire-Fighting Assistance 68 4.8 Security Measures 68 5.0 MAINTAININGEMERGENCY PREPAREDNESS . . . . . . . . . . . .,. . . . 80 5.1 Emergency Plan and Plant Emergency Procedures 80 5.1.1 Responsibility for the Planning Effort 80 5.1.2 Emergency Plan and Plant Emergency Procedures Update and Changes 81 5.1.3 Updating Telephone Listings 81 5.1.4 Plant Emergency Procedures . . . . . . . . . . . . . . 81 5.1.5 NUREG-0654 Cross-Reference . . . . . . . . . . . . . ~ 81 5.1.6 Annual Independent Audit 81 5.2 Emergency Plan Training Program 81
- 5. 2. 1 General Requirements 81 5.2.2 Deleted 82 5.2.3 Off-Site Organizations 83 5.2.4 Emergency Planning Coordinator and Staff Training 83 5.2.5 Public Education and Information CP&L 83 5.2.6 Public Information State of North Carolina 84 5.3 Drills and Exercises 84 5.3.1 Drills 84 5.3.2 Exercises 85 5.4 Maintenance and Inventory of Emergency Equipment and Supplies 86 6.0 RECOVERY 87 6.1 General 87 6.2 Recovery Organization 87 6.3 Assignment of Responsibilities 87 6.4 Recovery Plan Activation 91 6.5 Recovery Planning 92 6.6 Reentry Planning 92 6.7 Total Population Exposure Estimates 93 6.8 Recovery Termination and Reporting Requirements 93 PLP-201 Rev. 26 Page 5 of 131
Table of Contents (continued)
Title Pacae
7.0 REFERENCES
95 ANNEX A Agreements 96 ANNEX B Technical Basis of Emergency Dose Projection Program 97 ANNEX C Glossary of Terms 105 ANNEX D NUREG-0654 Rev. 1 Cross-Reference . . . . . . . . . . . . 111 ANNEX E List of Plant Emergency Procedures (PEP) 117 ANNEX F Emergency Notification Form (DELETED) 119 ANNEX G- Interfacing Information from Supporting Emergency Plans 120 ANNEX H Operations Map Shearon Harris Nuclear Power Plant 131 PLP-201 Rev. 26 Page 6 of 131
List of Tables Number Title Pacae 1.8-1 Demographic Information by Subzone 16 1.8-2 HNP Plume Exposure EPZ Evacuation Time Estimates 20 2.2-1 On-Shift Staffing for Emergencies . . . . . . . . . . . . . . 41 3.1-1 Typical Emergency Supplies Available for Emergency Facilities 4.0-1 Off-Site Agency Support Summary 69 4.2-1 Execution of Unusual Event 71 4.2-2 Execution of Alert 72 4.2-3 Execution of Site Emergency 73 4.2-4 Execution of General Emergency 74 4.5-1 Protective Action Guidelines (PAGs) for the Early Phase 75 4.5-2 Protective Action Guides for the Ingestion Pathway 76 4.6-1 CP&L Radiation, Contamination, and Exposure Limits 77 B.l-l Source Term Categories 103 B.1-2 Radiation Monitors Used As Radioactive Release Indicators . . 104 G.l-l Organizations Participating in Emergency Response . . . . . . 126 PLP-201 Rev. 26 Page 7 of 131
List of Fi ures Number Title Pacae 1.5-1 Ingestion Exposure Emergency Planning Zone (50-Mile EPZ) 13 1.5-2 Plume Exposure Emergency Planning Zone (10-Mile EPZ) 1.5-3 HNP Site Plan and Emergency Facilities 15 1.8-1 Demographic Information by Sector 17 1.8-2 Hospital and Family Care Facilities Located in the HNP 10-Mile EPZ 18 1.8-3 Schools Located in the HNP 10-Mile EPZ 19 2.2-1 On-Site Emergency Response Organization 43 2.4-1 Off-Site Emergency Response Organization 4.1-1 Emergency Action Level Flow Path, Side 1 78 4.1-2 Emergency Action Level Flow Path, Side 2 79 6.2-1 Recovery Organization 94 G-1 Emergency Response Organization Interfaces, TSC and EOF not Activated 128 G-2 Deleted 129 G-3 Emergency Response Organization Interfaces, TSC and EOF Activated 130 ANNEX H Operations Map - Shearon Harris Nuclear Power Plant 131 PLP-201 Rev. 26 Page 8 of 131
1.0 INTRODUCTION
1' Authorit /Re uirements The Harris Nuclear Plant (HNP) Emergency Plan and Plant Emergency Procedures have been prepared in accordance with the following requirements and guidelines:
Code of Federal Regulations, 10CFRSOg Section 50.47, "Emergency Plans."
- b. Code of Federal Regulations, 10CFR50, Section 50.54(q),
"Conditions of Licenses."
Code of Federal Regulations, 10CFR50, Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities."
- d. NUREG-0654, FEMA-REP-1, Revision 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," November 1980.
e ~ NUREG-0737, Supplement 1, "Requirements foz Emergency Response Capability", December 17, 1982.
FEMA Guidance Memorandum MS-1, "Medical Services," Federal Emergency Management Agency, November 13, 1986.
g~ RTM-92, "Response Technical Manual" Volume 1, Revision 2, U.S.
Nuclear Regulatory Commission, Washington, D. C., October 1992.
IE Information Notice 85-55, "Revised Emergency Exercise Frequency Rule, " July 15, 1985.
EPA-400-R-92-001, "Manual of Protective Action Guidelines and Protective Actions for Nuclear Incidents," U.S. Environmental Protection Agency, May 1992.
7 ~ EPPOS No. 1, "Emergency Preparedness Position (EPPOS) on Acceptable Deviations from Appendix 1 of NUREG-0654 Based Upon the Staff's Regulatory Analysis of NUMARC/NESP-007, 'Methodology for Development of Emergency Action Levels'".
1.2 Pur ose of HNP Emer enc Plan and Procedures The purpose of the HNP Emergency Plan (E-Plan) and Plant Emergency Procedures (PEPs) is to assure that the state of on-site and off-site emergency preparedness provides reasonable assurance that adequate corrective and protective measures can and will be taken in the event of a radiological emergency at the plant. The HNP E-Plan and Procedures outline the Emergency Preparedness Program which has the following objectives:
Protection of plant personnel and the general public.
Prevention or mitigation of property damage.
Effective coordination of emergency activities among all organizations having a response role.
- d. Early warning and clear instructions to the population-at-risk in the event of a serious radiological emergency.
PLP-201 Rev. 26 Page 9 of 131
1.2 Pur ose of HNP Emer enc Plan and Procedures (continued)
Continued assessment of actual or potential consequences both on site and off site.
- f. Effective and timely implementation of emergency measures.
go Continued maintenance of an adequate state of emergency preparedness.
The HNP E-Plan and PEPs are contained in the HNP Plant Operating Manual (POM) and consist of the following parts:
Volume 1, Part 2, Emergency Plan (PLP-201)
Volume 2, Part 5, Plant Emergency Procedures (PEP)
A list of PEPs required to implement the plan can be found in Annex E of the Emergency Plan.
1.3 Res onsibilit for Plan Develo ment and Review Responsibility for the HNP Emergency Plan development, review, and periodic update is assigned to the Supervisor Emergency Preparedness who serves as the HNP Emergency Planning Coordinator.
1.4 Emer enc Classes Off-normal plant conditions are classified according to four emergency classes which in order of increasing severity are UNUSUAL EVENT; ALERT; SITE EMERGENCY; and GENERAL EMERGENCY. The emergency classes are defined in NUREG-0654, Appendix 1, as follows:
- a. Unusual Event Unusual events are in process or have occurred which indicate a potential degradation of the, level of safety of the plant. No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs. Unusual Event is equivalent to the NRC designated class "Notification of Unusual Events."
- b. Alert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to small fractions of EPA Protective Action Guideline exposure levels. The Alert class may correspond to failure or jeopardy of one Fission Product Barrier.
c Site Emer enc Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near site boundary. Site Emergency is equivalent to the NRC designated class "Site Area Emergency." The Site Emergency Class may correspond to failure or jeopardy of two Fission Product Barriers.
PLP-201 Rev. 26 Page 10 o f 131
1.4 Emer enc Classes (continued)
- d. General Emer enc Events are in process or have occurred which involve actual or imminent substantial core degradation oz melting with potential for loss of containment integrity. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels off site for more than the immediate site area. The General Emergency class may correspond to failure or jeopardy of three Fission Product Barriers.
Events that could lead to any of these emergency classifications aze described in Section 4.0, "Emergency Measures and Operations."
1.5 Plant Site Descri tion The Harris Nuclear Plant (HNP) site is located in the extreme, southwest corner of Wake County, North Carolina, approximately 16 miles southwest of Raleigh, which is the largest population center, and approximately 15 miles northeast of Sanford, North Carolina, in Lee County (See Figures 1.5-1 and 1.5-2).
Approximate coordinates of the plant centerline are latitude 35'38'01" N and longitude 78'57'23" W. The Harris Nuclear Plant consists of one pressurized water reactor (PWR) of Westinghouse Corporation manufacture, licensed to operate at 2775 megawatts thermal (MWt). The associated net electrical output is approximately 900 megawatts electric (MWe). The major structures of HNP which contain radioactive materials are the Containment Building, Reactor Auxiliary Building, Fuel Handling Building, and the Waste Processing Building.
Figure 1.5-3 shows the principle site buildings.
Figure 1.5-2 shows the Exclusion Area Boundary (EAB) and the location of the Harris Energy & Environmental Center (HE&EC) in which the Emergency Operations Facility (EOF) is located.
1.6 Plume Ex osure Emer enc Plannin Zone (EPZ)
The Plume Exposure Emergency Planning Zone (EPZ) is defined as the area within an approximate 10-mile radius of the HNP and is referred to as the 10-Mile EPZ.
Principal exposure sources from the plume exposure pathway are (a) external exposure to gamma and beta radiation from the plume and from deposited materials and (b) exposure of the internal organs to gamma and beta radiation fzom inhaled radioactive gases and/or radioactive particulates. The time of potential exposure can range in length from hours to days.
Figure 1.5-2 shows the Plume Exposure EPZ in relation to the location of HNP.
The Plume Exposure EPZ includes portions of the North Carolina counties of Chatham, Harnett, Lee, and Wake. Annex H, attached, shows evacuation routes and local emergency planning zone boundaries in the 10-mile EPZ.
The prevailing winds around the plant are from the southwest.
1.7 In estion Ex osure Emer enc Plannin Zone The Ingestion Exposure Emergency Planning Zone (EPZ) is defined as the area within an approximate 50-mile radius of the HNP and is referred to as the 50-Mile EPZ.
The ingestion exposure sources from the ingestion pathway are contaminated water or food, such as milk or fresh vegetables. The time of potential exposure can range in length from hours to months.
PLP-201 Rev. 26 Page 11 of 131
1.7 In estion Ex osure Emer enc Plannin Zone (continued)
Figure 1.5-1 shows the 50-mile Ingestion Exposure EPZ in relation to the location of the Shearon Harris Plant. The Ingestion Exposure EPZ includes the North carolina counties of Alamance, Caswell, Chatham, Cumberland, Durham, Franklin, Granville, Guilford, Harnett, Hoke, Johnston, Lee, Montgomery, Moore, Nash, Orange, Person, Randolph, Robeson, Sampson, Vance, Wake, Wayne and Wilson.
The region within a 50-mile radius of the HNP site contains both urban and rural areas with industry, farming, business, education, research, and military interests.
1.8 Demo ra hic Information The distribution of resident population in the 10-Mile Emergency Planning Zone is presented in Table 1.8-1 and Figure 1.8-1. Special facilities within the Plume Exposure Emergency Planning Zone are depicted in Figures 1.8-2 and 1.8-
- 3. The 10-Mile Emergency Planning Zone evacuation time estimates are provided in Table 1.8-2.
1.9 Su ortin Emer enc Plans Emergency Plans which support this Plan are:
a North Carolina Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Division of Emergency Management, Department of Crime Control and Public Safety.
- b. U.S. Nuclear Regulatory Commission, NUREG-0728, NRC Incident Response Plan.
- c. Federal Radiological Emergency Response Plan.
- d. Southern Mutual Radiological Assistance Plan.
- 1. 10 FSAR Commitment Cross-Reference FSAR Section: Emergency Plan Section:
a 0 9.5.2.2 13.2.3.2.2 5.3.1
- c. 13.3 Emergency Plan (all)
PLP-201 Rev. 26 Page 12 of 131
Figure 1.5-1 Ingestion Exposure Emergency Planning Zone (50-Mile EPZ)
III
~
treil wero I
~ ~
IO I 4 Nrosvl Cnot tttN I Ilrr IclAIQI+ OiveoN I 4 I Ovvrlt~
~ elwv Wow I Swiss I I
>I O~ Orev eoreIrt I I n
/o Isert II I
~ vo eo I I
/
L. F 0 R D I
I I ~ I I isle 0'llwr~I re F
4stwrs L I Oo ISO %~ I I--
I S R
~
~.l
~
II 6
llwe t
I Cwvoo I AL MAN
~ a s lill ON vsw Woo 1
toev Ceres I' vtIre I tet Erw x I
,+ tllsro I4S ~
tt i Oerrrw Xeoe a jhm- Ra ei iree ~ rv I I It ~ Ones Vew N
~ recess
~NI
+
II Neret vnw sate Ikavvr I fso 4V II terr~I I SHNP ~ I re C Ieehoerr 4 I Ii SITE WWVVSrle I rwev trios l 0 H N I 7
' lIVeorll NV ~eliot toecneo reorerw tones v' II Srxitt<I I /
~ I + s a 2~ vlgyaf oslo
'4 tsrrol
/
tvv ONI
~~t,L ~ \
E f II 4ee 0 0 R '\ I Seeress
~ ~H A R I
r It I I ERY I
~ 0 ereoee II~ terreeo NV Creel I I r/I~
~ / W,Al I I I
~
I I
'eretlleare it )%Watt
~ I ererrrl Cenw ore reel r4I rr I lr Foe ~
I 5 A N p 5 0 SN I t I C HMOND IO Oioto I o xs r<<
+
I 'I I lei ~ Il leos s
S I~
S CA LE IN M I LES PLP-201 Rev. 26 Page 13 of 131
Figure 1.5-2 Plume Exposure Emergency Planning Zone (10-Mile EPZ)
P'
~
r ~~.
~ I4I
, J'
~ '
"I 4 P 'rr PITTSBORO, I
r, 9
r) /
<<.~)I
~ .
CHARON /
EXCLUSION 8 ~
~ r h AREA I 4 SOVNPARY .~:
r SH HARRIS ENERGY ANO
'NVIRONMENTAL
~ tr ~ CENTER SITE r 4 rr ~
I IW
'r
~ ~
I
~,d' ( IJ I
la r
+ ~ ~
W
~ ~
rr I ~
4 Y I ~
10-MILE RAOIUSI
~
1~.
'r I
I ~ rrr
~ '
0'*NPORO
~ rr j C I ULLINGTON )I '
PLP-201 Rev. 26 Page 14 of 131
Figure 1.5-3 HNP Site plan and Emergency Facilities 10 e 0000 00 3 2 QOO 16 14 12 18 13 r
L<------" - )
waaahaiaaaaa illII EEllQIII ItBIIIIRIIIII IIIIIIIlIIIIIHIIIIIIII 1 Reactor Containment Building 2 Turbine Building (First Aid Room on ground floor, 3 Reactor Auxiliary Building North end) 4 Operations Building 5 Main Control Room 6 Fuel Handling Building 7 Waste Processing Building (OSC in HP Tech 8 Diesel Generator Building Work Area) 9 Security Building (Normal Evacuation) 10 K Building (TSC on 4th Floor) ll 12 Administration Building (Admin Building Assembly Area)
Service Building 13 Bulk Warehouse 14 Water Treatment Building 15 Switchyard 16 Cooling Tower 17 Helicopter Landing Zone 18 Evacuation Monitoring Area 19 Protected Area Boundary PLP-201 Rev. 26 Page 15 of 131
Table 1.8-1 Demographic Information by subzone POPULATION SUB-ZONE PEAK PEAK PERMANENT SEASON TOTAL A 2,150 2,150 1,140 50 1,190 129 10 139 180 55 235 10,786 1,661 12,447 2,589 65 2,654 7,336 513 7,849 2,184 250 2,434 508 20 528 948 15 963 768 1,153 1,921 474 5,769 6,243 1,333 3,605 4,938 810 4,541 5,351 TOTAL: 29,185 19,857 49,042 Population estimates are based on a 1989 survey Rev. 26 Page 16 of 131
Figure 1.8-1 Demographic Information by Sector
~1828
~4343 N
NNW 10 MILES NNE
~632 1533
~4393 NW 4104 NE 4127 5 MILES WNW 272 ~2973 1 47 ENE 78 239 2872 2 IL 26 23 11 98 2 27 7 3
~659 w s76 76 7 6 2981 E ~3037 2 9 0 0 0 0 0 81
~
707 5127 WSW 85 103 ESE 82 ~5199 470 1290 SW SE 939
~450 ~1042 POPULATION TOTALS Distance (Miles) Po ulation Total Miles Total Po ulation 0-2 141 0-2 141 2-5 1860 0-5 2001 5-10 27183 0-10 29184 NOTE: Data is based on a 1989 survey.
PLP-201 Rev. 26 Page 17 of 131
Figure 1.8-2 Hospital and Family Care Facilities Located in the HNP 10-Mile EPZ
~NNW ~NNE
~NW
~NE
~WNW 15 IRENE 14 10 13 12 1 ml.
~wsw 08 ~ESE 015
~sw ~SE 10 ml.
~ssw ~SSE 1 Adam's Family Care ¹1 and ¹2 9 Mathew's Family Care 2 Atwater's Rest Home 10 Francis Morning's Family Care 3 Brown Family Care 11 Morrison's Family Care 4 Brighton Mannor 12 Mims Family Care Home 5 - Comfort Care 13 Our Golden Ladies 6 James Rest Home 14 Rose Haven Rest Home 7 - Lyles'amily Care 15 Seagraves Family Care 8 Mary's Family Care Home 16 Wake Hospital 'outhern PLP-201 Rev. 26 Page 18 of 131
0 Figure 1.8-3 Schools Located in the HNP 10-Mile EPZ n ~NNE
~NW
~NE
~WNW
~ENE 0 Pe
~
~wsw GEESE
~sw ~SE 10 ml.
~ssw CASSE 1 Apex Elementary 5 Fuquay-Varina Middle 2 Apex High 6 Fuquay-Varina High 3 Apex Middle 7 Lincoln Heights Elementary 4 - Baucom Elementary 8 Moncure Elementary PLP-201 Rev. 26 Page 19 of 131
Table 1.8-2 HNP Plume Exposure EPZ Evacuation Time Estimates Evacuation Times (Hrs. + Min.)
Weather Condition: Good Adverse Summer Summer Summer Late Fall Sub-zones Description Weekday Weekend Evening Weekday 2-mile radius 2+30 2+ 30 1 + 40 2 + 40 A,B,C 5-mile 90 NE 2+45 2+45 2 + 40 3 + 00 A,C,D 5-mile 90 SE 2+45 2+45 2 + 40 2 + 50 A,K 5-mile 90 2+45 2+45 2 + 50 2 + 50 A,B,K,L 90 NW SW'-mile 2+45 3+ 10 2+ 50 3+ 10 A,B,C,D,K,L 5-mile radius 2+45 3+10 2+ 50 3+ 10 A,B,C,D,E,F,G 10-mile 90 NE 3+25 3+15 3 + 05 4 + 20 A,C,D,G,H,K 10-mile 90 SE 3+10 3+ 15 3 + 05 3 + 30 A,K,J,I 10-mile 90 SW 2+ 50 2+ 50 2 + 50 2 + 55 A,B,K,L,M,N 10-mile 90 NW 3+ 15 3+ 35 2+ 50 3+15 All Entire EPZ 3+25 3+35 3+05 4+ 20 Evacuation times include notification and alerting of the public via primary means (15 minutes), mobilization and preparation of the public for evacuation, and evacuation to the outer boundary of all the local planning zones being evacuated.
Source: Evacuation Time Estimates for the Plume Exposure Pathway Emergency Planning Zone:
Shearon Harris Nuclear Power Plant, Rev. 3, October 1990.
2.0 ORGANIZATION AND RESPONSIBILITIES 2.1 General There are requirements for action in an emergency that go beyond those encountered during routine operations. To meet these additional demands and provide an effective response to the emergency, the HNP Emergency Plan employs an organizational concept that has four features.
a Whenever the Plan is activated, a single individual is charged with the responsibility'or and the authority to direct all actions necessary to respond to the emergency.
- b. The primary responsibility of the individual in charge is to assure that all emergency response functions are carried out.
Upon activation of the Plan, he is freed of all other responsibilities and thus able to devote his entire effort to managing the emergency response.
Specific individuals are assigned the responsibility of carrying out predefined critical actions and emergency measures.
- d. There is a mechanism established to provide additional resources as necessary to respond to the emergency, which provides continuity of response on each critical action.
This concept of organization is compatible with and integrated into the normal mode of operation. The shift operating crew is routinely required to correct minor malfunctions of equipment and to diagnose the consequences of radioactivity releases. There are a number of procedures to guide operators in responding to equipment malfunctions and instrument alarms. There are also procedures to maintain effective control over contamination and radiation exposures. Emergency procedures basically involve an extension of these existing plant procedures.
2.2 Emer enc Or anization 2.2.1 Cor orate Emer enc Or anization The emergency 'response resources available to respond to an emergency consist of the personnel at the plant, at Corporate Headquarters, at other Company nuclear plants, the Harris Energy a Environmental Center and, in the longer term, at other organizations involved in the nuclear industry. Throughout CP&L there exists a staff of well-trained and experienced engineers, scientists, and technicians. These personnel represent a pool of technical expertise that can be called upon to provide additional support to the corporate emergency response and recovery organizations, if required.
2.2.2 On-Site Emer enc Res onse Or anization The plant Emergency Response Organization (ERO) is composed of a broad spectrum of personnel with specialties in operations, maintenance, engineering, radiochemistry, health physics, material control, fire protection, security, and emergency planning. The greatest number of personnel with these specialties are available during day shift operations; however, needed specialists can be recalled to the site at any time.
The first line of defense in responding to an emergency lies with the normal on-duty operating shift when the emergency begins. Shift members are assigned defined emergency response roles, as shown in Table 2.2-1, that are to be assumed whenever an emergency is declared. As additional personnel are called in to the plant, a smooth transition occurs since each individual knows ahead PLP-201 Rev. 26 Page 21 of 131
2.2.2 On-Site Emer enc Res onse Or anization (continued) of time what their responsibilities- will be. A current call list of ERO members is maintained in the Main Control Room and procedures are available to activate the ERO automatically or manually.
The Company is committed to providing staffing to effectively contain any emergency which might occur at its nuclear facilities. Depending on the emergency at hand, personnel with required expertise will be contacted on a priority basis as shown in Table 2.2-1. Additional personnel will be available to provide communications, on-site and off-site radiological assessment, repair and corrective actions, and technical support within a short period of time. Depending on weather conditions, 30-45 minutes should provide enough time to make the appropriate staff available to augment the plant on-shift organization. The plant ERO will continue to be augmented such that within 60-75 minutes after notification, additional personnel will be added to provide the necessary support. Additional personnel will continue to supplement the on-site ERO as necessary to meet the requirements of this Plan.
The fully augmented on-site ERO is shown in Figure 2.2-1 and personnel assignments are provided in Table 2.2-1 and/or procedures. The, on-site ERO utilizes the basic plant organization structure as the principle guideline in emergency assignments. This philosophy assures whenever possible, that personnel will be performing emergency functions that are similar to their normal operating duties. Each emergency position has a succession of command from assigned, trained alternates.
2.3 Command and Control The position of Site Emergency Coordinator is activated for command and control purposes upon declaration of an emergency. Until relieved by the Emergency Response Manager, the Site Emergency Coordinator is delegated the authority to act on behalf of the Company to manage and direct all emergency operations involving the facility. Upon activation of the Emergency Operations Facility, the Emergency Response Manager assumes responsibility of overall emergency response and performs those requirements for all off-site related activities. The Site Emergency Coordinator maintains overall on-site emergency responsibilities including emergency classification and, after EOF activation, reports to the Emergency Response Manager.
The Superintendent Shift Operations on duty at the time the emergency is declared shall initially assume the position of Site Emergency Coordinator from the Main Control Room.
The following conditions for command and control apply:
Zf the Site Emergency Coordinator becomes incapacitated for any reason, a designated alternate shall assume the position of Site Emergency Coordinator.
- b. Once the Technical Support Center is activated the General Manager-Harris Plant or his designated alternate assumes the position of Site Emergency Coordinator.
The Site Emergency Coordinator, or Emergency Response Manager after the EOF is activated, may not delegate the responsibility to make the decision to notify and make recommendations to authorities responsible for off-site measures.
PLP"201 Rev. 26 Page 22 o f 131
2.3 Command and Control (continued)
While he may consult with others, the Site Emergency Coordinator may not delegate the responsibility to determine the classification of an emergency condition.
The Site Emergency Coordinator is authorized to request Federal and State assistance until the EOF is activated, whereupon such requests are made under the direction of the Emergency Response Manager.
NOTE: Zf deemed prudent in order to ensure an adequate response to the emergency, the Site Emergency Coordinator Control Room may direct that the TSC and/or EOF assume responsibility for any/all discrete functions prior to reaching full staffing levels or to activate only those functions which he feels are necessary for an adequate emergency response.
The conditions for transfer of designated responsibilities from the Superintendent Shift Operations (Site Emergency Coordinator Control Room) to the Site Emergency Coordinator TSC and the Emergency Response Manager (EOF) are:
- 2) The Site Emergency Coordinator - TSC and the Emergency Response Manager have received a briefing on the status of the emergency.
2.4 Assi nment of Res onsibilities All emergency response personnel with responsibilities listed in 2.4.1 through 2.4.10.5 will:
a Be assigned responsibility for these positions in accordance with PEP-407, or the Superintendent - Shift Operations Program.
- b. Be trained and qualified to perform the assigned responsibilities as specified in Section 5.2.
Be formally relieved by a qualified alternate trained for duty in the particular position before leaving that position.
- d. Maintain a record of activities where appropriate.
2.4.1 Su erintendent Shift O erations Until an emergency is declared, the Superintendent Shift Operations has the following responsibilities relating to the Emergency Plan:
Direct the activities of the Operations staff.
Recognize an off-normal condition as indicated by instrument readings or observation.
c implement any Emergency Operating Procedures.
Determine when an Emergency Action Level has been met or exceeded, declare an emergency, and assume the position of Site Emergency Coordinator.
PLP-201 Rev. 26 Page 23 of 131
2.4.2 Site Emer enc Coordinatoz The primary person assigned to the position of Site Emergency Coordinator during the initial stages of an emergency is the Superintendent,- Shift Opezations. The assigned alternates are on-shift Licensed Senior Control Operators as designated in accordance with PEP-102. Once the TSC is activated the primary person assigned to the position of Site Emergency Coordinator is the General Manager Harris Plant. The assigned alternates are filled by personnel designated in accordance with PEP-407.'he Site Emergency Coordinator, located in either the Main Control Room (MCR) or Technical Support Center (TSC), shall perform the following functions:
- a. Request assistance from Immediate Response Organizations as needed (This function stays in the Main Control Room after the activation of the TSC).'.
Classify the emergency.
ce Designate an individual to be in charge of the Main Control Room (MCR).
Coordinate and direct the activities of emergency response personnel in the MCR, TSC, Operational Support Center (OSC) and elsewhere on the plant site.
- e. Order the alerting of on-site personnel and the evacuation of nonessential personnel from local areas or the site when conditions warrant.
Order the activation of the TSC, the OSC, and the EOF, when required.
- g. Ensure required notifications are made in a timely manner.
- h. Ensure adequate manning, access control, and 24-hour functional continuity of the MCR, the TSC, and the OSC, when activated.
Approve planned radiation exposures for on-site personnel in excess of 5 rem TEDE or entry into radiation fields greater than 25 rem/hr.
Review and approve deviations from Technical Specifications or license conditions if the Site Emergency Coordinator is a Superintendent - Shift Operations, or ensure that a Superintendent Shift Operations approves such deviations.
Authorize the Radiological Control Director (or alternate) to administer potassium iodide to on-site emergency workers.
Request additional material, manpower, and equipment as necessary.
Designate an individual to brief the NRC Site Response Team upon their arrival to the site, if applicable.
Declare the emergency terminated when the situation is under control in consultation with appropriate agencies.
0 ~ Keep the Nuclear Regulatory Commission informed as to the status of the plant.
PLP-201 Rev. 26 Page 24 of 131
2.4.2 Site Emer enc Coordinator (continued)
- p. Perform the functions of the Emergency Response Manager until activation of the Emergency Operations Facility (EOF) occurs.
This includes:
~ When contacted by the State or Counties, after an initial notification of an emergency, brief the State and Counties on plant conditions and actions being taken.
~ Recommend protective actions which should be taken by the public to off-site government authorities.
~ Keep Corporate Communications and appropriate State and local agencies informed as to the status of the plant and radiological effects off site.
~ Keep the Nuclear Regulatory Commission informed of the radiological effects off site.
~ Provide updates to the State of N.C. and Counties on the emergency condition and recommendations for protective actions at approximately 30- to 60-minute intervals, or necessary, more frequently.
if Keep the Emergency Response Manager informed when the Emergency Operations Facility is activated.
Ensure that he is relieved only by an individual trained to perform the duties of Site Emergency Coordinator.
2.4.3 Plant O erations Director The Plant Operations Director, located in the Main Control Room, is responsible to the Site Emergency Coordinator for providing direction to the Main Control Room Staff, the Fire Brigade, and the First Aid Teams.
Specifically, the Plant Operations Director shall:
a 0 Direct Main Control Room personnel in determining the nature and extent of emergencies pertaining to equipment and plant facilities.
- b. Ensure immediate corrective actions are carried out by Main Control Room personnel to minimize the consequences of the emergency.
c ~ Ensure adequate staffing of the Main Control Room.
Analyze plant parameters for trends.
Organize and direct rescue operations of injured personnel by the First Aid Team or Search and Rescue Team.
Ensure fire brigade actions are in accordance with the Fire Plan and fire area preplans.
Request support from the Technical Analysis Manager, as necessary, after the EOF is activated.
- h. Ensure that deviations from Technical Specifications or License Conditions are approved by a Superintendent Shift Operations qualified individual.
PLP-201 Rev. 26 Page 25 of 131
2.4.3.1 Technical Anal sis Director The Technical Analysis Director (TAD) reports to the Site Emergency Coordinator and is located in the Technical Support Center.
The TAD shall:
- a. Supervise the Accident Assessment Team.
Monitor and evaluate vital plant parameters during an emergency to determine the overall condition of safety-related systems, the core, and fission product barriers.
c Monitor emergency conditions for changes in Emergency Action Level status and recommend to the SEC any changes in the emergency classification when conditions so indicate.
Develop special procedures needed to reduce the consequences of an emergency condition.
Coordinate recommendations to the SEC from the Accident Assessment Team.
2.4.3.2 Accident Assessment Team The Accident Assessment Team reports to the Technical Analysis Director and is located in the Technical Support Center. The Team is composed of a Shift Technical Advisor and representatives from the Core Performance, Electrical/1&C and Mechanical engineering disciplines.
2.4.3.3 Fire Bri ade Team Leader A Fire Brigade Team Leadex is established on all shifts. When a fire occurs, the Fire Brigade Team Leader is the on-scene commander for fighting the fire and di.rects the activities of the Fire Brigade. The Fire Brigade Team Leader reports to the Main Control Room. The Fire Brigade Team Leader shall:
- a. Directly supervise the Fire Brigade Team during fire emergencies.
- b. Keep the Main Control Room informed on the status of the fire emergency.
c, Request and coordinate the fire-fighting resources from off-site fire agencies through the Main Control Room.
'I Communicate with the Main Control Room as frequently as necessary to ensure:
(1) Awareness of the approach to, or exceeding of, an Emergency Action Level caused by the fixe or fire-fighting efforts.
(2) Awareness of effects on safe shutdown equipment from the fire or fire-fighting efforts.
(3) Awareness of changes in radiological conditions that could affect fire-fighting efforts.
- e. Maintain awareness of personnel participating in the Fire Brigade and their location.
I Assume responsibility for direction and control of off-site responding fire department personnel.
PLP-201 Rev. 26 Page 26 of 131
When a fire is announced, the Fire Brigade reports to the Fire Brigade Team Leader. If a fire occurs, the Fire Brigade goes to the Fire Staging Area where fire-fighting equipment is located, and then goes to the fire scene.
The fire brigade is composed of on-shift personnel trained in fighting fires as described in Section 5.2.
2.4.3.5 First Aid Team A First Aid Team is established on all shifts. The First Aid Team reports to the Main Control Room. The First Aid Team has the following responsibilities:
- a. Perform/coordinate emergency first aid and search and rescue activities.
- b. Assess necessary medical aid required from off-site sources and advise the Main Control Room.
- c. Deleted by Revision 25.
2.4.3.6 O erations Leader The Operations Leader is in charge of Control Room activities related to control of the plant and provides direction to on-shift Operations personnel.
The Operations Leader reports to the Plant Operations Director when the Technical Support Center is activated and otherwise to the Site Emergency Coordinator.
2.4.4 Emer enc Re air Director The Emergency Repair Director, located in the Operational Support Center, is responsible to the Site Emergency Coordinator for providing direction to the Damage Control Coordinator and the Damage Control Team Leaders. The Emergency Repair Director shall:
a Direct the total on-site maintenance and equipment restoration effort fr'om the OSC.
- b. Maintain command and control of the OSC.
Identify and develop required steps or procedures that need to be implemented to reduce the consequences of and recovery from an emergency situation.
Ensure that maintenance work activities are coordinated with the Radiation Control Coordinator and Plant Operations Director (when operations support is needed).
Ensure that equipment is maintained during an emergency.
Evaluate, in coordination with the Radiological Control Director and Radiation Control Coordinator, a new location for the OSC in case the OSC needs to evacuate.
Ensure that accountability of OSC personnel is maintained during an emergency.
Ensure that adequate numbers of ERO personnel are available in the OSC to support the emergency.
PLP-201 Rev. 26 Page 27 of 131
2.4.4.1 Dama e Control Coordinator The Damage Control Coordinator located in the Operational Support Center (OSC) is responsible to the Emergency Repair Director for providing direction to the Damage Control Team Leaders, Maintenance Planners, OSC Storekeeper and OSC Logkeeper. The Damage Control Coordinator shall:
Determine the extent of damage to equipment and recommend corrective action(s) to the Emergency Repair Director.
Dispatch Damage Control Teams, located in the OSC, to the plant after properly briefing the teams on the mission to be performed.
Direct and monitor the activities of the Damage Control Teams through their Damage Control Team Leaders.
Maintain accountability of Damage Control Team personnel when they are outside of the OSC.
- e. Direct and monitor the activities of the Maintenance Planners.
Keep the Emergency Repair Director informed of the status of repair and restoration work being performed.
Coordinate maintenance activities with the Radiological Control Coordinator.
- h. Identify any additional supplies or equipment needed to perform assigned functions.
2.4.4.2 Dama e Control Team Leaders The Electrical/I&C and Mechanical Damage Control Team Leaders assemble initially in the OSC and are responsible to the Damage Control Coordinator for on-the-scene supervision of the Damage Control Teams to which they are assigned. The Damage Control Team Leaders shall:
- a. Assess the nature and extent of damage incurred.
- b. Perform emergency zepairs.
ce Perform actions to reduce the effect of the emergency, or to slow down a radiological release, when repair is not possible.
Assure that procedures, drawings, schematics, tools, Emergency Radiation Work Permits, and other documentation necessary foz the team's specific mission are provided as necessary.
Assure that all Damage Control Team members are properly outfitted with equipment necessary for their missions (such as, dosimeters, hard hats, flashlights, hand-held radio).
2.4.4.3 Dama e Control Teams The Damage Control Teams are dispatched by the Damage Control Coordinator, from their initial assembly point in the OSC, to the scene of an emergency repair or damage assessment requirement.
The Damage Control Teams report to the on-scene Damage Control Team Leader and are composed of mechanical, instrument and control, and electrical maintenance personnel.
PLP-201 Rev. 26 Page 28 of 131
2.4.4.4 Deleted by Revision 25 2.4.4.5 Maintenance Planners Maintenance planners assemble in the OSC and report to the Damage Control Coozdinator. The maintenance planners are responsible for developing plans for emergency repair, determining spare parts needed to make the repairs, estimating the amount of time required to perform the emergency zepairs.
2.4.4.6 OSC Storekee er The OSC storekeeper assembles in the OSC and reports to the Damage Control Coozdinatoz. The OSC Storekeeper is responsible for expediting the spare parts and tools needed in support of OSC activities.
2.4.5. Securit Director The Security Director, normally located in the TSC, reports to the Site Emergency Coordinator and is responsible for the following activities:
a ~ Maintain plant security in accordance with the provisions of the HNP Security Plan and Safeguards Contingency Plan.
Perform accountability of TSC and Security Force personnel and coordinate the accountability of personnel inside the Protected Area.
Identify to the Site Emezgency Coordinator any non-routine security procedures and/or contingency conditions that are in effect or that require a response.
- d. Provide personnel, as available, for search teams for missing personnel. Identify areas and routes for searching in coordination with the Radiological Control Director.
Provide personnel, as available, for emergency assessment and repair teams in gaining access to plant areas as required.
- f. Effect liaison with local law enforcement agencies.
ge Provide necessary members of the Security Force to maintain access control at the EOF when activated.
Ensure the locations of security team personnel are verified frequently by Security Force supervision.
Generate periodic listings of personnel within the Protected Area via the Security Computer.
Provide personnel for escorts of emergency vehicles that may be required to enter the protected area.
- k. Notify personnel outside of the Protected Area, but inside the Exclusion Area Boundary, at a Site or General Emergency.
Coordinate Security Force activities with the Radiological Control Director to ensure that security personnel comply with Emergency Radiation Work. Permit requirements.
PLP-201 Rev. 26 'Page 29 of 131
2.4.5.1 Admin Buildin Assembl Area Leader The Admin Building Assembly Area Leader is responsible to the Admin and Logistics Manager, or prior to activation of this position, the Site Emergency Coordinator, for the following actions:
- a. Coordinate the activities in the Admin Building Assembly Area.
When requested, direct appropriate personnel to travel to emergency facilities to augment the ERO.
c Coordinate the evacuation of personnel located in the Admin Building in the event of a Site or Exclusion Area evacuation.
2.4.6 Radiolo ical Control Director The Radiological Control Director is responsible to the Site Emergency Coordinator for providing direction to the Chemistry Coordinator and the Radiological Control Coordinator. The Radiological Control Director has an Assistant to help in performance of his responsibilities.
The Radiological Control Director shall:
Direct the Radiological Control Team, and Chemistry Team to accumulate, tabulate and evaluate data on plant conditions such as radiation monitoring readings, hazardous material surveys, and other pertinent data.
Ensure use of protective clothing, respiratory protection, and access control within the plant as deemed appropriate to control personnel exposures.
c>> Ensure that appropriate bioassay procedures have been implemented for on-site personnel when a radiological incident has occurred.
Ensure that personnel are decontaminated, if necessary.
Assist, in the transfer of contaminated injured personnel and nonessential personnel.
Determine appropriate on-site personnel evacuation routes and alternate Assembly Areas when deemed necessary.
Ensure planned exposures in excess 'of 5 rem TEDE or entry into radiation fields greater than 25 rem/br are approved by the Site Emergency Coordinator.
Manage administration of radioprotective drugs (potassium iodide) to members of the Emergency Response Organization when authorized by the Site Emergency Coordinator.
Ensure that potentially contaminated on-site foodstuffs are surveyed and isolated as appropriate.
2.4.6.1 Moved to Section 2.4.10.3.2 2.4.6.2 Moved to Section 2.4.10.3.5 2.4.6.3 Moved to Section 2.4.10.3.3 2.4.6.4 Moved to Section 2.4.10.3.4 PLP-201 Rev. 26 Page 30 of 131
2.4.6.5 Chemistr Coordinator The Chemistry Coordinator, located in the OSC, is responsible to the Radiological Control Director for providing direction to the Chemistry Team during an emergency.
The Chemistry Coordinator shall:
Assign personnel to operate the Post-Accident Sampling System (PASS) and obtain and analyze other samples as requested by the Radiological Control Director.
- b. Provide data to the Accident Assessment Team and the Dose Projection Team from analyses of samples of plant systems.
Maintain personnel accountability of the Chemistry Teams when they are outside of the Operational Support Center.
'd. Identify any additional supplies or equipment needed to perform assigned functions.
2.4.6.6 Chemistr Team Chemistry Teams report to the Chemistry Coordinator and are composed of plant chemistry personnel. They assemble initially in the Operational Support Center and are subsequently dispatched to sampling stations, the PASS Panel, and the laboratory.
2.4.6.7 Radiolo ical Control Coordinator The Radiological Control Coordinator, located in the Operational Support Center, is responsible to the Radiological Control Director for providing direction to the Radiological Control Teams during an emergency. The Radiological Control Coordinator may appoint an assistant who may perform some of the following functions. The Radiological Control Coordinator shall:
Assign personnel to accompany Damage Control Teams and reentry teams as required to provide health physics coverage.
Ensure that radiological and chemical habitability conditions in the Assembly Areas are monitored when required.
c ~ Direct the decontamination of contaminated personnel and/or on-site areas and equipment as necessary.
Direct the administration of radioprotective drugs to on-site personnel after receiving direction from the Radiological Control Director.
Ensure that access control is provided for radiological areas where necessary. Establish control points, monitoring points, and decontamination areas.
- f. Establish temporary dosimetry issue areas where necessary.
Establish protective clothing and respiratory protection requirements for all on-site emergency personnel.
PLP-201 Rev. 26 Page 31 of 131
2.4.6.7 Radiolo ical Control Coordinator (continued)
Assist the First Aid Team in evaluating the management of contaminated injured personnel, and notify the Radiological Control Director when transportation of a contaminated injured person is required.
- i. Maintain accountability of Radiological Control Team members when they are outside the OSC.
- j. Provide personnel to conduct in-plant radiological surveys.
- k. Monitor the Radiation Monitoring System and maintain a record of significant and unusual area radiation levels.
Identify any additional supplies or equipment necessary to perform assigned functions.
2.4.6.8 Radiolo ical Control Teams Radiological Control Teams report to the Radiological Control Coordinator and are composed of health physics personnel. They assemble initially in the Operational Support Center and are subsequently dispatched wherever personnel radiation control and decontamination functions are needed.
2.4.7 Emer enc Communicators Emergency Communicators are located in the Main Control Room, Radwaste Control Room, Technical Support Center, and the Emergency Operations Facility and are responsible to the Site Emergency Coordinator (or the Emergency Response Manager in the EOF).
2.4.7. 1 Emer enc Communicator - Control Room Initially, an on-shift operator is appointed by and reports to,the SEC EC-CR.
Control Room (Superintendent Shift Operations) to fill the position of Responsibilities of the Emergency Communicator Control Room include communicating with:
Off-site authorities (County, State, NRC, and so forth) to perform required notifications of the declaration/upgrading of an emergency prior to the activation of the TSC and EOF.
The plant Emergency Response Organization (during off-hours) when CP&L emergency facilities are being activated.
C. Local Immediate Response Organizations (medical, fire, law enforcement, and so forth) if their assistance is needed.
2.4.7.2 Communications Director The Communications Director, located in the Technical Support Center, reports to the Site Emergency Coordinator Technical Support Center and is responsible for providing direction to the Emergency Communicator NRC, two Status Board Plotters and the Admin Team.
The Communications Director shall:
PLP-201 Rev. 26 Page 32 of 131
2.4.7.2 Communications Director (continued) a Ensure that timely notifications are sent to the NRC, as per PEP-301, upon the declaration of an emergency and each subsequent upgrading or downgrading of the emergency.
- b. Perform Public Address announcements on a periodic basis to keep on-site personnel informed on the status of the emergency.
Ensure that Status Board Plotters post current plant and off-site information on status boards located in the TSC.
Ensure that emergency communications equipment on site is functioning properly.
- e. Ensure that communications equipment is used to support the emergency and that unnecessary non-emezgency communications are terminated.
Ensure that TSC Directors are kept informed of HNP requests for support from off-site Immediate Response Organizations.
- g. Direct the overall activities of the Administrative Team.
- h. Coordinate plant support for the NRC Site Response Team.
2.4.7.3 Communications Mana er The Communications Manager, located in the Emergency Operations Facility, reports to the Emergency Response Manager and is responsible for providing direction to the Emergency Communicator State/County, Emergency Communicator Corp Comm/JIC and two Status Board Plotters.
The Communications Manager shall:
a Ensure that timely notifications are sent to the State and Counties, as per PEP-301, upon the declaration of an emezgency and each subsequent upgrading or downgrading of the emergency.
- b. Ensure that Status Board Plotters post current plant and off-site information on status boards in the EOF.
Ensure that emergency communications equipment used by EOF personnel is functioning properly.
Ensure that timely updates are provided to Corporate Communications and/or the JIC as necessary.
- e. Ensure that notifications are sent to outside agencies (such as, INPO, ANZ, and so forth) as per PEP-301.
2.4.8 Joint Information Center Staff The Joint Znformation Center (JZC) organization (see Figure 2.4-1) is headed up by the Company Spokesperson. The Company Spokesperson and the Company Technical Spokesperson are the key corporate media spokespersons. The responsibilities of these positions are described below. Personnel staffing the JIC are appointed in accordance with PEP-407.
PLP-201 Rev. 26 Page 33 of 131
2.4.8. 1 Com an S okes erson The Company Spokesperson reports to the Emergency Response Manager in the EOF and has the JIC Director reporting directly to him. The Company Spokesperson has the following responsibilities:
Maintaining command and control of the JIC to include adequate staffing levels and ensuring that personnel are periodically briefed on the status of the emergency.
Ensure that the composition and timeliness of J
- b. CP&L News Releases are adequate.
Ensure that the release of information is coordinated with the various Public Information Officials (PIOs) located in the JIC.
- d. Provide accurate and timely information to the news media through formal briefings.
2.4.8.2 JIC Director The JIC Director has the following responsibilities:
- a. Directing the activities of the Company Technical Spokesperson, the Administrative Coordinator, the News-Coordinator, and the Public Information Coordinator.
- b. Scheduling the JIC staff briefings with the Company Spokesperson.
c Coordinating the flow .of information from the JIC to Corporate Communications, the State, and County PIOs.
- d. Acting as Company Spokesperson, if required.
Com an P'.4.8.3 Technical S okes erson The Company Technical Spokesperson has the following responsibilities:
- a. Supervise the activities of the Technical Specialist.
Assist in gathering information from the EOF for CP&L news releases and media briefings.
Provide timely and accurate technical information to the, media during formal briefings.
Brief the JIC Staff when directed to do so by the Company Spokesperson or JIC Director.
2.4.8.4 Administrative Coordinator The Administrative Coordinator reports to the JIC Director and directs the activities of the Administrative Assistants and Media Badging Specialist.
The Administrative Coordinator has the following additional responsibilities:
Ensuring that the JIC is set up in a functional manner and resolving any facility problems that arise.
- b. Coordinating shift turnover staffing with the Administrative and Logistics Manager in the EOF.
PLP-201 Rev. 26 Page 34 of 131
2.4.8.4 Administrative Coordinator (continued)
Directing JIC Security.
2.4 '.5 News Coordinator The News Coordinator has the following responsibilities:
Monitoring the information flow from the EOF for CP&L news releases and media briefings.
Preparing CP&L news releases.
c ~ Verifying that news release information is approved by the Emergency Response Manager in the EOF.
Coordinating the release of news information from the JIC with the Company Spokesperson.
- e. Transmitting approved CP&L news releases to Corporate Communications.
2.4.8.6 Public Information Coordinator The Public Information Coordinator reports to the JIC Director and directs the activities of the Public Information Specialists.
The Public Information Coordinator has the following additional responsibilities:
Ensuring that the JIC staff is provided with necessary clerical materials.
- b. Coordinating with the State Lead Rumor Control/Lead PIO Phone Coordinator in the JIC to ensure that CP&L and the State are not releasing conflicting information.
Co Maintaining an updated event status board for the Public Information Specialists.
2.4.9 Re resentatives to the State/Count Emer enc 0 erations Centers Personnel are assigned in accordance with PEP-407 as representatives to the State/County Emergency Operations Centers (EOC). The State and four county EOCs are located:
N.C. State EOC State Administrative Building in Raleigh, N.C., and is the principle Emergency Operations Center.
Wake County EOC Wake County Courthouse, Raleigh, N.C.
Chatham County EOC Law Enforcement Center, Pittsboro, N.CD Harnett County EOC Law Enforcement Center, Lillington, N.C.
Lee County EOC Sanford Municipal Center, Sanfordg N C.
These representatives act as technical liaisons capable of providing interpretations of emergency action levels, protective action recommendations made by the Site Emergency Coordinator or Emergency Response Manager.
PLP-201 Rev. 26 Page 35 of 131
2.4.10 Emer enc Res onse Mana er and Staff The EOF Emergency Response Organization is depicted in Figure 2.4-1.
Personnel staffing the EOF are appointed in accordance with PEP-407.
2.4.10.1 Emer enc Res onse Mana er The Emergency Response Manager, who is located in the Emergency Operations Facility, is responsible for relieving the Site Emergency Coordinator Control Room of interfacing with CP&L Corporate Communications, the Joint Information Center and off-site agencies (with the exception of the NRC Emergency Notification System (ENS) communications), and for managing and directing all off-site related emergency operations involving the plant upon activation of the Emergency Operations Facility.
The Emergency Response Manager is responsible for providing direction to the Technical Analysis Manager, Administrative and Logistics Manager, Radiological Control Manager, and Communications Manager.
Specifically, the Emergency Response Manager is responsible for:
a Notification, protective action recommendations, dose projection, environmental monitoring and contact with off-site support groups.
- b. Providing liaison between the Site Emergency Coordinator and off-site support personnel.
Marshalling off-site support as required to support the Site Emergency Coordinator.
Supervising a staff located in the Emergency Operations Facility with expertise in dose assessment, environmental monitoring, radiation control, technical analysis, administration, and logistics.
Briefing the State and Counties on plant conditions and actions being taken, as required, to augment the activities of the Communication Manager's Staff.
Recommending protective actions which should be taken by the public to off-site government authorities.
Providing updates to the State and Counties on the emergency condition and recommendations for protective actions at approximately 30- to 60-minute intervals, or frequently.
if necessary, more Ensuring that EOF and TSC personnel are updated on emergency conditions, recommendations foz protective actions, and plant conditions on a periodic basis.
Requesting assistance from Federal agencies.
Approve emergency personnel exposure EOF levels when it is likely that personnel or environmental monitoring team personnel will incur planned exposures in excess of 5 rem TEDE or will enter into radiological areas where the projected exposure rate exceeds 25 rem/br.
PLP-201 Rev. 26 Page 36 of 131
2.4.10.1 Emer enc Res onse Mana er (continued)
The Emergency Response Manager shall not delegate the responsibilities for deciding what protective actions to recommend to off-site authorities, or for notifying authorities responsible for off-site emergency measures. Other personnel may be assigned to assist and make recommendations; however, the final decision rests with the Emergency Response Manager.
2.4.10.2 Deleted by Revision 23.
2.4.10.3 Radiolo ical Control Mana er The Radiological Control Manager is responsible to the Emergency Response Manager for providing direction to the Dose Projection Team Leader and Technical Advisor.
Upon activation of the Emergency Operations Facility and Radiological Control Managers functions, the control and coordination of the environmental monitoring and Dose Assessment functions will transfer to the EOF from the Main Control Room.
The Radiological Control Manager is responsible for the following actions:
Assist in assessment of off-site radiological consequences of the event, utilizing information from available sources, and keep the Emergency Response Manager informed of the assessment.
- b. Provide dose calculations to the Emergency Response Manager for off-site areas based on data from available sources and/or mathematical modeling.
Provide off-site monitoring of radiological effluents in the environment as required.
Provide technical assistance to the Radiological Control Director located in the TSC, as needed.
Coordinate the design of special packaging required for the transport of radioactive wastes resulting from the emergency operation.
Provide information and recommendations to the Emergency Response Manager concerning future activities that could radiologically affect the plant or the environment.
Direct the administration of potassium iodide to off-site CP&L and contractor employees when authorized by the ERM.
- h. Recommend approval of emergency personnel exposure levels to the ERM when it is likely that Emergency Operations Facility personnel or Environmental Monitoring Team personnel will incur planned exposures in excess of 5 rem TEDE or will enter into radiological areas where the projected exposure rate exceeds 25 rem/hr.
2.4.10.3.1 Technical Advisor The Technical Advisor reports to the Radiological Control Manager in the EOF and is responsible for providing technical assistance as required.
PLP-201 Rev. 26 Page 37 of 131,
2.4.10.3.2 Dose Pro'ection Team Leader The Dose projection Team Leader, located in the EoF, is responsible to the Radiological Control Manager for directing the activities of the Environmental Field Coordinator and the Dose Projection Team.
The Dose Projection Team Leader shall:
Assign personnel to perform dose projection and source term calculations.
Interface with ERFIS, the Weather Center or the National Weather Service to obtain meteorological forecasts.
Provide dose projection related information for use in off-site protective action decision making.
- d. Interface with N.C. Division of Radiation Protection and NRC personnel in the EOF.
Direct the RC Team member(s) to perform habitability surveys and personnel monitoring in the EOF as needed.
Ensure that Environmental Monitoring Team activities are being coordinated by the Environmental Field Coordinator.
2.4.10.3.3 Environmental Field Coordinator The Environmental Field Coordinator in the EOF is responsible to the Dose Projection Team Leader for providing direction to the plant Environmental Monitoring Teams.
The Environmental Field Coordinator shall:
Direct the activities of Environmental Monitoring Teams by positioning them such that representative samples and surveys of, the plume, if any, can be made.
b, Advise team members of expected radiological conditions.
c Collect and evaluate Environmental Monitoring Team sample and survey data.
Provide the results of environmental samples and surveys to the Dose Projection Team Leader.
- e. Assist in the orderly assumption of the environmental monitoring function in the EOF.
Maintain a list of personnel assigned to each Environmental Monitoring Team and of Team locations.
Advise the Environmental Monitoring Team members of the need to take potassium iodide or don respirators made to do so.
if the decision has been 2.4.10.3.4 Environmental Monitorin Teams Environmental Monitoring Teams report to the Environm'ental Field Coordinator after EOF activation, or to the Site Emergency Coordinator - Control Room prior to EOF activation. Teams assemble at HE&EC and are subsequently dispatched in vehicles to the surrounding area.
PLP-201 Rev. 26 Page 38 of 131
2.F 10.3.5 Dose Pro'ection Team The Dose Projection Team reports to the Dose Projection Team Leader and is located in the Emergency Operations Facility. The Dose Projection Team is composed primarily of health physics personnel.
2.4.10.4 Technical Anal sis Mana er The Technical Analysis Manager reports to the Emergency Response Manager and is responsible for direction of activities of the EOF Senior Reactor Operator and the EOF ERFIS Operator.
The Technical Analysis Manager is responsible for the following actions:
- a. Provide technical support in assessing the cause of the emergency.
Provide technical support in systems analysis, core analysis, operating and maintenance procedure revisions, licensing information development and coordination, plant systems design data development, continued assessment of plant systems interaction, and continued determination of the safety status of the plant.
Co Coordinate the receipt and assessment of technical information related to plant systems and facility operations (from the plant and from outside organizations), and submit timely recommendations to the Emergency Response Manager for implementation.
Provide technical interface, as authorized by the Emergency Response Manager, to utility groups, consultants, technical investigation groups, and regulatory agencies.
Assess the impact of the incident on continued operation of other Company nuclear plants, and submit results of this assessment to the Emergency Response Manager for review and subsequent submittal to Corporate Management.
Establish a standby list of Company personnel to provide additional timely technical support as may be requested during the emergency response (Fuels/Core Analysis; Licensing; mechanical, electrical, instrumentation and control, and NSSS plant systems).
Develop out-of-normal operating and emergency procedures as requested.
2.4.10.5 Administrative and Lo istics Mana er The Administrative and Logistics Manager reports to the Emergency Response Manager and is responsible for direction of activities of the Administrative Team Leader and Administrative Team.
The Administrative and Logistics Manager is responsible for the following actions:
Provide assistance to the Emergency Response Manager and the Site Emergency Coordinator in the planning, scheduling, and expediting of the emergency response operations.
- b. Provide personnel to install, maintain, and operate communications equipment and emergency facilities (both on site and at the EOF and JIC) needed to carry out emergency response activities.
PLP-201 Rev. "26 Page 39 of 131
2.4.10.5 Administrative and Lo istics Mana er (continued)
- c. Provide purchasing personnel responsible for locating, ordering, and receiving equipment and materials needed to carry out emergency response activities (both on site and at the EOF and JZC) .
Provide processing of expense accounts, distribution of checks from payroll, and administration of other personnel financial aspects of the Emergency Response Organization.
Provide logistical arrangements for support personnel called in to assist in the emergency response operations, including communications hardware, transportation, room and board.
Coordinate with the Security Director the processing of support personnel that will be arriving in response to the emergency (such as, NRC, FEMA, contractors, and so forth).
Determine additional contracts, facilities, and services required by the Emergency Response Organization.
- h. Provide administrative services such as clerical, typing, and duplication.
- i. Provide authorization for access to Emergency Operations Facility.
Provide for accountability of Emergency Operations Facility personnel.
- k. Arrange for relief staffing for Emergency Response Organization personnel located in the TSC, OSC, EOF, and JlC.
2.4.10.6 Deleted by Revision 20.
2.4.10.7 Moved to 2.4.7.3 in Revision 25.
2.5 Outside Or anization Su ort Outside organizations that support HNP in an emergency are described in Annex G.
PLP"201 Rev. 26 Page 40 of 131
TABLE 2.2-1 ONNHIFT STAFFING FOR EMERGENCIES NUREG 0737 Supplement 1 Minimum Capability for Additions Emergency Function Emergency Positions Job Category Shift Size 3045 min 60-75 min
- 1. Emergency Direction Site Emergency Superintendent- Shift Operations" and Control Coordinator (SEC)
Senior Harris Site Management'nit
- 2. Plant Operations and Operations Leader Senior Control Operator (SCO) <~>
Assessment of Operational Aspects Superintendent - Shift Operations"'ontrol Operations Team Operators <.>
Auxiliary Operators" Senior Control Operator (SCO)~'ontrol Operators"'uxiliary Operators" >
- 3. Notification Emergency Plant Personnel Communication Communicator
- 4. Radiological Emergency Response Senior Harris Site Management Assessment Manager Dose Projection Team Environmental and Radiation Control Leader Personnel Environmental Environmental and Radiation Control Monitoring Team Personnel Personnel Radiological Control Environmental and Radiation Control Team Personnel Personnel (Surveys)
Chemistry Team Chemistry Personnel Personnel (Chemistry)
" BEFORE Activation of the Technical Support Center (Continued on next page)
"'FTER Activation of the Technical Support Center
TABLE 2.2-1 (continued)
NUREG 0737 Supplement 1 Minimum Capability for Additions Emergency Function Emergency Positions Job Category Shift Size 30-45 min 60-75 min
- 5. Plant Engineering Repair Accident Assessment Shift Technical Advisor and Corrective Actions Team Core Performance Engineering Electrical Engineering Mechanical Engineering Damage Control Mechanical Maintenance Team Personnel Electrical/IKC Maintenance
- 6. Protective Actions Radiological Control Radiation Control Team Personnel Personnel (exposure control)
- 7. First Aid and Rescue First Aid Team Operations Personnel Operations Other Personnel Local Rescue Support Other Off Site Support Personnel Local Support
- 8. Fire Fighting Fire Brigade Operations Personnel 5'er FSAR 9.5.1 Local Fire Support Other Off Site Support Personnel Local Support
- 9. Site Access Control Security Team Security Personnel All Per Security Plan CP8iL TOTAL(Less Security): 19 16 Note: 'May be provided by shift personnel who are also assigned other functions.
Eigure 2.2-1 On-Site Emergency Response Organization Site Control Room Emergency Coordinator OSC TSC Senior Reactor Socunity Operator Diroctor Security Officers Plant Emergency Radiation Technical Repair Ccntrd Anatysis Corruisr nications irector Director Director Dueclor Director SE~R & Danage Assistant AAT-Core Emerg Control Rad Con Ccmrisre&mor Weadef Coordinator Performance Director - NRC.
Emergecny DC Team Radiation . Status Communicatcr Leader- Ccntrol AAT-Electrical / t&C Board Plotter (Contrd Rm.) Mechanical Coordinator OAo C
Mechanical Assistanl Status Ccntrol Rad Con AAT- Board Ptdter Operatls Mantenance Coordinator Mechanical ~ Bo DC Team Radiaticn Leader- Ccntrol AAT- STA TSC E tee. / I &C Teanl Logkeeper Fire Brigade Team Leader TSC Eke. / I&C Chemistry ERFlS Adrnn Mantenance Coordinator Operator Team Fire Brigade Mantenance TSC Chemisky Computor Pkrnn era Team Support OSC Storekeeper Key Position Control Room/Operations Operations Support Centor Technical Support Center PLP-201 Rev. 26 Page 43 of 131
Eigure 2.4-1 Off-Site Emergency Response Organization Emergoncy EOF Response Managor Emergency Site Media Prepvedness Manager Admin a Technical Radiation Logistics Analysis Control Manager Manager Manager Admin Technical EC Rep. to Stato Team Leader EOF SRO Advisor (State/Cou~ EOC Admin Dose EC EOF ERFIS Projection Rep. to Wake Team Operator 5corp Comml Toom Loader IC) County EOC EOF Status Board Rep to Hamett Log keeper Plotter A County EOC Admin.Bldg, Assembly Environmental Status Board Rep to Lee Area Loader Field Coord. Plotter 8 County EOC Repto Chatham Key Position County EOC JIC Company Spokes porson JIC Director Company Admin News Public Technical Information Spokos person Coordinators Coor6inator Coordinator Tochnical Public Information Specialist Media Badglng S peoplet PLP-201 Rev. 26 Page 44 of 131
3.0 EMERGENCY FACILITIES, COMMUNICATIONS'ND EQUIPMENT 3.1 General The purpose of emergency response facilities is to provide centralized locations for organized command and control of on-site activities and off-site activities performed by the Company such as environmental monitoring.
Different groups within the Emergency Response Organization are provided with a location from where they may direct or perform the activities for which they are responsible while providing for coordination of activities with other organizations.
Adequate emergency facilities, communications, and equipment to support emergency response are provided and maintained. Carolina Power & Light Company (CP&L) Emergency Plans include provision for emergency response facilities as follows:
- Main Control Room (MCR)
- Operational Support Center (OSC)
Emergency Operations Facility (EOF)
- Joint Information Center (JIC)
The Main Control Room is an emergency response facility that is operational on a day-to-day basis. Initially the emergency actions and in plant response would be directed by the site Emergency Coordinator from the Main Control Room. Operations personnel would be dispatched from their work area located immediately north of the Main Control Room with assistance from on-shift health physics, maintenance, and security personnel as needed.
Operations' The facilities, other than the Main Control Room, are unmanned or used for other purposes on a day-to-day basis. In the event of an emergency, the TSC, OSC, EOF, and JIC would be activated in accordance with Section 4 of this Plan, "Emergency Measures and "
In addition to the emergency response facilities, provision is made for on-site and off-site geophysical phenomena monitors (meteorological and seismic); radiological monitors; process monitors; and fire and combustion products detectors for use in initiating emergency measures and assessing the emergency. Each of these are described in subsequent paragraphs of this Chapter. Typical emergency supplies available for emergency facilities are indicated in Table 3.1-1.
3.2 Main Control Room (MCR) 3.2.1 Characteristics
- a. Located in the Reactor Auxiliary Building as shown in Figure 1.5-3 Control Room habitability and radiation protection is as described in Section 6.4 of the FSAR 3.2.2 Functions Reactor and plant control
- b. Interim location for Site Emergency Coordinator PLP"201 Rev. 26 Page 45 of 131
3.2.2 Functions (continued)
- c. Accident recognition, classification, and mitigation
- d. Notification of off-site agencies
- e. Alerting of on-site personnel
- f. Initial dose projections
- g. Recommendations for immediate protective actions for the public Activation of HNP/CP&L emergency response facilities and recall of emergency personnel 3.2.3 Emer enc E ui ment and Su lies
- a. Main Control Board
- b. Emergency Response Facility Information System (ERFIS)
- c. Safety Parameter Display System (SPDS) (Part of ERFIS)
Measurement and Indication of Regulatory Guide 1.97 (Rev. 2) variables (ERFIS)
- e. Radiation Monitoring System (RMS)
- f. Fire Detection System (adjacent room)
- g. Seismic Monitoring Cabinet
- h. Gross Failed Fuel Detector Console
- i. Kitchen and sanitary facilities Reliable voice communications with the TSC, OSC, EOF, NRC Operations Centers, and State and local government 24-hour warning points.
- k. See Table 3.1-1 3.3 Technical Su ort Center (TSC) 3.3.1 Characteristics Located within the Protected area at Elevation 324'-0" in the Fuel Handling Building, Section "K," approximately 400 feet walking distance from the Main Control Room (MCR) (primary route).
- b. Protective clothing and portable breathing apparatus are kept in both the TSC and Main Control Room for personnel who must traverse between the two. Alternative paths are available that can be used based upon radiological conditions as determined by monitoring teams.
Exterior walls, roof, and floor are built to Seismic Category I, tornado, wind, and missile safety-related criteria.
PLP-201 Rev. 26 Page 46 of 131
3.3.1 Characteristics (continued)
- d. Provided with radiation protection equivalent to Main Control Room habitability r'equirements such that the dose to an individual in the TSC for the duration of a design basis accident is less than 5 rem TEDE. The Emergency Ventilation System includes HEPA and carbon filtration.
Environmentally controlled to provide room air temperature, humidity and cleanliness appropriate for personnel and equipment.
Reliable power for habitability systems and battery pack emergency lighting are provided.
- g. Equipment is nonsafety-related and nonredundant.
Designed taking into account good human factors engineering principles.
3.3.2 Functions
'a ~ Command center for Site Emergency Coordinator and his staff upon TSC activation. The TSC is officially activated by the Site Emergency Coordinator (SEC) when the necessary personnel and equipment are assembled at the TSC to carry out an emergency response function required by the emergency conditions.
- b. Receives and displays plant status and parameters data on ERFIS.
Ce Provides notifications to the NRC via Emergency Notification System.
Provides plant management and technical support to plant operations personnel.
- e. Directs emergency response teams in the plant.
Assists the Main Control Room in accident assessment.
Performs emergency classification.
3.3.3 Emer enc E ui ment and Su lies Reliable voice communications with the Main Contxol Roomy EOFg OSC, NRC Operations Center and state and local government 24-hour warning points as described in Section 3.8 which follows.
- b. Video System capable of displaying ERFIS information (such as, plant data, SPDS, and RMS) as discussed in Section 3.9.1.
c ~ Reference materials including Mechanical and Electrical Systems Drawings; Plant Operating Manual; FSAR; Corporate, Plant, State, and Local Emergency Plans; and a Document Services Library.
Decontamination and monitoring area.
Survey meter and area radiation monitor.
Fax and photocopier equipment.
See Table 3.1-1.
PLP-201 Rev. 26 Page 47 of 131
- 3. 4 0 erational Su ort Center (OSC) 3.4.1 Characteristics aI Located in the Waste Processing Building inside the Protected Area (Figure 1.5-3).
- b. The total area is approximately 1500 square feet in the Waste Processing Building HP Tech Work Area. This area includes a separate Command and Control area for coordinating and planning of OSC activities in addition to sufficient area for team members to standby for activities. Additional space in excess of 8500 square feet is available in adjacent offices and locker rooms to accommodate additional personnel as may be required c ~ Alternate locations include the Safety Meeting Room, Diesel Generator 2A Building, or Technical Support Center.
3.4:2 Functions Assembly location for emergency teams for receipt of special equipment and assignments.
- b. Dispatching of emergency teams.
3.4.3 Emer enc E ui ment and Su lies Reliable voice communications with the Main Control Room, EOF, and TSC.
- b. Supplies and equipment as shown in Table 3.1-1.
I 3.5 Emer enc 0 erations Facilit (EOF) 3.5.1 Characteristics Located at Hazris Energy & Environmental Center within 10 miles of the plant (see Figure 1.5-2).
Approximately 4800 square feet of space for approximately 70 persons including 10 NRC personnel.
Shielded to a protection factor (PF) of 5 and ventilated with an Emergency Ventilation System, with HEPA and carbon filtration, such that the total 30 day dose from all sources of a design basis accident for an individual in the EOF does not exceed 5 rem TEDE or its equivalent to any other part of the body.
- d. Structurally built in accordance with Uniform Building Code.
- e. Environmentally controlled to provide room air temperature, humidity, and cleanliness appropriate for personnel and equipment.
Backup power for habitability systems and battery pack emergency lighting are provided.
g Provided with security to maintain readiness and to exclude unauthorized personnel when activated.
Designed taking into account good human factors engineering principles.
PLP-201 Rev. 26 Page 48 of 131
3.5.1 Characteristics (continued)
Alternate assembly area location for EOF staff is the 11th floor of Center Plaza Building in Raleigh, N.C.
3.5.2 Functions
- a. Command center for Emergency Response Manager and his staff.
Upon activation, performs off-site notification, protective action recommendations, environmental monitoring, and dose projection.
- c. Emergency communications systems monitoring and control.
- d. Provides technical analysis and support.
- e. Receives and displays plant status and parameters data on ERFIS.
- f. Serves as the Recovery Center during recovery operations.
3.5.3 Emer enc E ui ment and Su lies a ~ Reliable voice communications with the TSC, Main Control Room, OSC, NRC Operations Centers and State and local government 24-hour warning points as described in Section 3.8.
Video system capable of displaying ERFIS information (such as, plant data, SPDS, and RMS) as discussed in Section 3.9.1.
Co Reference materials including Mechanical and Electrical Systems Drawings; Plant Operating Manual; FSAR; Corporate, Plant, State, and Local Emergency Plans.
- d. Decontamination and monitoring area.
- e. Survey meter and dosimetry.
Maps showing evacuation routes, evacuation areas, preselected radiological sampling and monitoring points, relocation centers in host areas, and shelter areas.
- g. Fax and photocopier equipment.
- h. Additional equipment as discussed in Section. 3.8.2.
- i. See Table 3.1-1.
3.6 Joint Information Center (JIC)
Located at the Civic Center in downtown Raleigh, approximately 21 miles from the plant, with a media briefing room available for press conferences.
Serves as the primary location for accumulating accurate and current information regarding the emergency conditions and writing news releases.
c Provides work space and phones for public information personnel from the state, counties, NRC, FEMA, and industry-related organizations.
- d. Provides telephones for use by the news media personnel.
- e. Is tied into CP&L emergency communications network.
PLP-201 Rev. 26 Page 49 of 131
3.6 Joint Information Center (JIC) (continued)
Provides responses to media inquiries through media communicators who staff telephones that the media can call for information about an emergency.
Implements provisions for rumor control by providing a number of telephones which members of the public, who hear rumors, can call for factual information.
Prior to JIC activation the required public information functions will be performed by the Corporate Communications Department in Raleigh 3.7 Non-CP&L Facilities 3.7.1 North Carolina-State Emer enc Facilities 3.7.1.1 North Carolina State Emer enc 0 erations Center (SEOC)
Assembly location for Governor, State Emergency Response Team and other officials as described in the State of North Carolina Emergency Response Plan.
Primary location for the coordination with federal, state, local authorities, and HNP as described in the State of North Carolina Emergency Response Plan.
c ~ Located at the Division of Emergency Management Headquarters, 116 W. Jones Street, Raleigh, North Carolina.
3.7.1.2 State Emer enc Res onse Team (SERT) a A designated staff of specialists who assist State officials as described in the State of North Carolina Emergency Response Plan.
- b. Located at the Division of Emergency Management Headquarters, 116 W. Jones Street, Raleigh, North Carolina.
3.7.2 Count Emer enc 0 erations Centers 3.7.2.1 Chatham Count Emer enc 0 erations Center (EOC)
Located in the Law Enforcement Center in Pittsboro Functions are described in the State of North Carolina Emergency Response Plan 3.7.2.2 Harnett Count Emer enc 0 erations Center (EOC)
Located in the Harnett County Law Enforcement Building in Lillington.
Functions are described in the State of North Carolina Emergency Response Plan.
3.7.2.3 Lee Count Emer enc 0 erations Center (EOC) a ~ Located in the Police Department of the Sanford Municipal Center, Sanford, N.C.
- b. Functions are described in the State of North Carolina Emergency Response Plan.
PLP-201 Rev. 26 Page 50 of 131
3.7.2.4 Wake Count Emer enc 0 erations Center (EOC)
- a. Located in the Wake County Courthouse in Raleigh.
- b. Functions are described in the State of North Carolina Emergency Response Plan.
3.8 Communications S stems 3.8.1 Plant Communications S stem A description of the plant communications systems is contained in Section 9.5.2 of the FSAR and consists of the following:
'a ~ Private Automatic Branch Exchange (PABX) Telephone System covering the Main Control Room, TSC, EOF, and OSC.
- b. Site paging system (accessed by Telephone System).
- c. Sound-powered telephone system.
- d. Two radio communications networks, one for security and one for operations.
Dedicated radio system from security center to local law enforcement agencies.
Plant PABX telephone system is powered from batteries charged by a rectifier.
- g. Backup power is provided to fixed radio equipment.
3.8.2 Harris Ener and Environmental Center PABX Tele hone and Other Radio
~Sstems The Harris Energy & Environmental Center (HE&EC) PABX telephone system includes:
(1) The HE&EC Private Automatic Branch Exchange (PABX) telephone system covers the Main Control Room, TSC, EOF, and OSC.
(2) An off-site Notification System (Selective Signalling System) provides communications to State and County warning points and Emergency Operations Centers from the Main Control Room, TSC, EOF, and Auxiliary Control Panel.
(3) The HE&EC PABX telephone system is powered from batteries charged by a rectifier.
- b. Other Radio Systems (1) Radio communications (separate from plant radios) 'with mobile and portable units used by the Environmental Monitoring Teams.
(2) Radio communications on the State Environmental Monitoring and Area B Channels.
(3) Mobile and portable radios are battery-powered.
PLP-201 Rev. 26 Page 51 of 131
3.8.3 Off-Site Communications S stems Off-site communications systems include:
- a. Corporate Telephone Communications system is interconnected with plant PABX and utilizes microwave transmission equipment.
Commercial telephone connections to PABX, emergency telephone system, dedicated lines to emergency facilities, and lines to the Joint Information Center.
- c. Load Dispatcher Radio Communications.
- d. NRC Emergency Notification System (ENS) Phone.
- e. NRC Health Physics Network (HPN) Phone.
3.8.4 Dialo ic Communicator Automated Notification S stem A computerized emergency response personnel call out computer is available to notify the CP&L Emergency Response Organization personnel and the NRC resident inspector of emergency declarations at the plant. The system provides instructions for activation of the on-site emergency facilities and the near site Emergency Operations Facility. Provisions aze provided for remote activation of the system via telephone lines and for password protection from unauthorized use of the system.
3.9 Assessment E ui ment Use of the equipment described in this section during an emergency will be detailed in Plant Procedures.
3.9.1 Emer enc Res onse Facilities Information S stem (ERFIS) and Safet Parameter Dis la S stem (SPDS)
The Emergency Response Facility Information System (ERFIS) provides the data acquisition capability and data base for performing plant monitoring and Safety Parameter Display System functions. The system is designed to scan, convert to engineering units, make reasonability and alarm limit checks, apply required transformations, store for recall and analysis, and display the reading of transformed data from plant instrumentation. The system scans flows, pressures, temperatures, fluid levels, radiation levels, equipment and valve status at required frequencies. Scanned variables are quality tagged.
The system provides for short and midterm storage of data to disk media for on line retrieval and fast recall and long-term storage to magnetic tape media.
The ERFIS consists of two redundant central processing units, two high capacity data disc drives, two medium capacity system disk drives, two magnetic tape drives, and associated interfaces, data links, remote multiplexors, data concentrators, and associated displays, keyboards, consoles, printers, and other devices. The system is configured to support fail over to backup units for critical hardware, thus providing maximum availability for the ERFIS. The system is powered from an uninterruptible power supply (UPS), with battery, that is powered from a normal plant power source. ERFIS displays and terminals aze located in the Main Control Room, Technical Support Center, and Emergency Operations Facility.
PLP-201 Rev. 26 Page 52 of 131
3.9.1 Emer enc Res onse Facilities Information S stem (ERFIS) and Safet Parameter Dis la S stem (SPDS) (continued)
The Safety Parameter Display System (SPDS) is a software subsystem of the ERFIS. The SPDS consists of a top-level display showing the status of Critical Safety Function Parameters at all times and a general display area for a summary display, graphic display of status trees, or plots of key parameters. An assigned SPDS display is provided in the Main Control Room and ERFIS terminals in any location can display SPDS with a single key stroke.
The SPDS will access all available signals and will display information related to:
- 1. Subcriticality
- 2. Coze Cooling
- 3. Heat Sink
- 4. (Reactor Vessel) Integrity
- 5. Containment
- 6. (Reactor Coolant System) Inventory Secondary displays will consist of graphic representations of the above critical safety functions and their status.
Additional detail and design criteria for the SPDS are provided in Item I.D.2 of the FSAR TMI Appendix.
3.9.2 Seismic and H drolo ical Data HNP has two distinct and separate seismic monitoring systems for the site. A seismic monitoring system, described in Section 3 '.4 of the FSAR, is located inside safety-related structures and measures horizontal and vertical acceleration. A second system, consisting of two free field strong motion detectors, is located at points on-site and must be read locally at each location. The recorded analog signal can be put on tape playback in the control room.
The design basis flood, probable maximum precipitation, and other improbable, conceivable extremes in hydrologic natural phenomena are well below any design limits for this site. Refer to FSAR Sections 2.4.2 and 2.4.3.
The CP&L Corporate Office can coordinate hydrology and seismology expertise.
3.9.3 Radiolo ical Monitorin The Radiation Monitoring System (RMS) is a plant-wide radiation information gathering and control system encompassing the process and effluent monitors and the area and airborne monitors. Radiological monitors are provided for plant systems as described in the FSAR Sections 11.5 and 12.3.4 Effluent radiological monitors are provided for:
Plant Vent Stacks Turbine Building Drains Tank Area Drain Transfer Pumps Treated Laundry and Hot Shower Tank Pumps Secondary Waste Sample Tank Main Steam Lines PLP-201 Rev. 26 Page 53 of 131
3.9.3 Radiolo ical Monitorin (continued)
The types, ranges, and locations of monitors are listed in Tables 11.5.2-1, 11.5.2-2 and 12.3.4-1 of the FSAR.
Typical portable radiation monitors and laboratory equipment are described in Section 12.5 of the FSAR.
The locations of the normal off-site and on-site environmental monitoring stations, and the location of the TLD monitoring stations are described in the Off-Site Dose Calculation Manual. Additional predetermined emergency off-site monitoring locations are contained in environmental monitoring procedures.
The Radiation Monitoring System, (RMS) provides the necessary activity or radiation levels required for determining source terms in dose projection procedures. The RMS is data linked to the ERFIS and radiation monitoring channel values are available in the TSC and EOF via ERFIS. The isotopic mix is based upon a default mix discussed in Annex B. PASS grab samples and on-site or off-site monitoring samples can then be analyzed to determine the true isotopic mix and the results used in the computerized dose projection software.
3.9.4 Normal and Post-Accident Sam lin S stem (PASS)
A normal operating primary and secondary sampling system and a post-accident sampling system has been provided and is described in Sections 6.2.5 and 9.3.2 of the FSAR. The normal sampling system samples are taken from the RCS Hot Leg, Pressurizer, Accumulator, Volume Control Tank, Steam Generator Blowdown Lines (3), RHR pump discharge, Main Steam Lines (3), Letdown Line, and at other primary and secondary system locations, The liquid PASS can sample reactor coolant from the Reactor Coolant System and from the Reactor Sump.
Analysis of samples from the PASS will provide a confirmatory means for identifying the various key isotopes listed in RTM-92 and PEP-362.
3.9.5 Meteorolo ical Instrumentation The plant has a permanent meteorological monitoring station located within the exclusion area boundary for display and recording of wind speed, wind direction, and differential temperature for use in making off-site dose projections. Meteorological information is presented in the Main Control Room, the TSC, and the EOF by means of a computer. Additional information on the on-site meteorological monitoring system can be found in Section 2.3.3 of the FSAR.
Carolina Power & Light Company has the capability to access the National Weather Service on a 24-hour-per-day basis to provide backup should the on-site system fail. This backup source of meteorological data is the closest location which can provide reliable representative meteorological information.
The Weather Center (Murray and Trettel Weather Service, Inc.) may be contacted during severe weather periods. The center analyzes national and local weather in order to provide localized weather forecasts for the System or for the HNP area as appropriate. The meteorologists can provide forecasts and current data reflecting conditions corresponding to their evaluation of weather data received from the National Weather Service and other sources. The NRC and State agencies may contact the Weather Center for appropriately formatted and checked meteorology data (current and forecasted) for the HNP area.
PLP-201 Rev. 26 Page 54 of 131
3.9.5 Meteorolo ical Instrumentation (continued)
In the event that the on-site meteorological tower or monitoring instrumentation becomes inoperative and the meteorologists cannot be contacted, meteorological data may be obtained directly from the National Weather Service in Raleigh, North Carolina.
3.9.6 Field Monitorin E ui ment Field monitoring equipment will have at least the capability to detect and measure radioiodine in the vicinity of the plant site as low as 1 x 10'Ci/cm'. An individual exposed to this concentration for a period of one hour would receive an exposure of about 0.2 rem or less, a value well below Protective Action Guideline (PAG) levels (See Section 4). A standard air sampler can collect about 0.03 pCi of I-131 in 10 minutes at a concentration of 1 x 10 'Ci/cm~, which can easily be measured by hand survey meters that utilize probes such as the HP-210. This is a simple test that can serve as an initial check of projected releases based on plant data and can confirm that significant quantities of elemental iodine have been released (the chemical form that would pose a health hazard) . More detailed measurements (such as, Sodium Iodide scintillation counters) can be brought into service to provide the longer term higher capabilities to detect and measure very low levels of contamination in the environment, as would be planned for subsequent radiation monitoring efforts.
3.9.7 Laborator Facilities Support of the on-site radiation monitoring and analysis effort is provided by an on-site laboratory. The on-site laboratory is the central point for receipt and analysis of all on-site samples and includes equipment for chemical analyses and for analysis of radioactivity. Section 12.5 of the FSAR provides information on'aboratory facilities.
Additional facilities for counting and analyzing HNP samples can be provided by the H.B. Robinson Nuclear Plant and the Brunswick 'Nuclear Plant. These laboratories can act as backup facilities in the event that the plant's counting room and laboratory become unusable during an emergency.
Other plant assessment equipment includes:
Fire Detection System (FSAR Sections 9.5.1 and 9.5.A)
Gross Failed Fuel Detection System Security Systems (Security Plan)
Metal Impact Monitoring System (FSAR Section 5.4.6.4)
PLP-201 Rev. 26 Page 55 of 131
TABLE 3 '-1 TYPICAL EMERGENCY SUPPLIES AVAILABLE FOR EMERGENCY FACILITIES Supplies MCR TSC JZC OSC EOF 7 Day su ly of food and water.
Protective Clothin (Anti-Cs)
Air Sam lin e ui ment Full face respirators Self-contained breathin e ui ment High and low range portable radiation survey instruments Emergenc ersonnel monitorin dosimetry Contamination control supplies such as si ns, tags, ro e, ta e, various forms Decontamination su lies First Aid Kit Portable Communications Equipment Radio Radio'" Radio"'emotes Remotes Remotes Batter - Powered Lanterns Polaroid Camera Mechanical and electrical systems drawings, Plant Operations Manual FSARg g
Cor orate, State & Local Emergency Plans 10-mile EPZ Area ma s of Plant Emergency Plan and
"'opy Procedures /( ~) /(d)
Environmental Monitoring Kit Potassium Zodide Tablets
/ Indicates equipment/supplies available in this facility Portable radio transceivers can be supplied to any emergency facility Stored at the Harris E&E Center
"'nnex H of Emergency Plan in the MCRg wall maps in other facilities.
Procedures Only JZC implementing procedure and emergency phone list only PLP-201 Rev. 26 Page 56 of 131
4.0 EMERGENCY MEASURES AND OPERATIONS Execution of the HNP Emergency Plan involves a variety of functions including emergency classification, notification, activation, assessment, protective response actions, and recovezy. Recovery is discussed in Section 6 of this Plan.
State and local governments and other agencies provide support in implementing the emergency measures in this section as shown in Table 4.0-1 and Annex G.
4.1 Emer enc Classification The four classes of emergency are Unusual Event (equivalent to NRC Notification of Unusual Event), Alert, Site Emergency (equivalent to NRC Site Area Emergency), and General Emergency. The operating staff is provided formal training to recognize off-normal plant conditions and categorize them within the parameters of the four emergency classes.
Emergency action levels are based upon the fission product barrier concept.
The three barriers that protect the public from a release of radioactive fission products (fission product barriers) are the fuel cladding, the reactor coolant system boundary, and the containment. This concept has its basis in NUREG-0654, Appendix 1 where emergency events are found that correspond to failures or jeopardy of the three basic fission product barriers. The concept used is that if any one of the fission product barriers are in jeopardy or breached, an Alert will be declared. If any combination of two barriers are either in jeopardy or breached, a Site Emergency is declared. If all three are in any combination of jeopardy or breach, a General Emergency is declared.
The categorization of events in NUREG-0654, Appendix 1 for Unusual Even'ts are separately evaluated as they do not directly correspond with failure or jeopardy of a fission product barrier. In addition to looking at the status of fission product barriers, the emergency action levels include the NUREG-0654 emergency action level events that are external to the plant, (natural or man-made disaster phenomena), or are not directly attributable to the condition of the reactor, (shutdown systems, fire, dose projections).
The categorization of events according to one of the four emergency classes is implemented through the Emergency Action Level (EAL) system. The system is composed of two subsystems: The Unusual Event Action Level Matrix and the EAL Network/Flow Path. The Unusual Event Action Level Matrix provides a set of plant conditions and events which coincide with the conditions associated with the Unusual Event. The Unusual Event Action Level Matrix is presented at the bottom of Figure 4.1-2. For the upper three emergency classes, the Emergency Action Level (EAL) System uses an integrated set of flowchart instructions.
As with the Unusual Event Action Levels, the EAL System also associates plant conditions and events with the three upper classes of emergency, but it so through a symptomatic (vice diagnostic) methodology using critical safety does function status trees.
This allows the EAL System to interface smoothly with the Emergency Operating Procedure (EOP) Network, thus assuring the rapid and correct classification of emergencies. Figures 4.1-1 and 4.1-2 are the flowcharts which together form the EAL Network. Abnormal Operating Procedures, Functional Restoration Procedures, End Path Procedures, and Flow Path Procedures contain specific direction for using the EAL Network whenever conditions warrant. A Plant Emergency Procedure provides the Unusual Event Action Levels, the EAL Network, the EAL Flow Path, as well as instructions for using them.
The Site Emergency Coordinator (or the Superintendent Shift Operations when no emergency has been declared) will declare any one of the four emergency classes where EALs have been exceeded, or in his judgment, the status of the plant warrants such a declaration.
PLP-201 Rev. 26 Page 57 of 131
4.2 Notification a The warning message form to the State and Counties is contained in PEP-301 and provides information required by NUREG-0654, II.E.3 and 4. The form is approved by the Site Emergency Coordinator Control Room or Emergency Response Manager after EOF activation and provided to the appropriate Emergency Communicator (EC-Control Room or EC-State/County) as a message text.
- b. The Emergency Communicator will use the Selective Signalling System phone to simultaneously notify the 24-hour-per-day, manned, State and County Warning Points with the notification message.
This message will be initiated to all Counties and the State within 15 minutes for all emergency classifications.
c The North Carolina Emergency Response Plan in Support of the Harris Nuclear Power Plant describes procedures for State and Local officials to make a public notification decision promptly (within about 15 minutes) on being informed by the plant of an emergency.
- d. Deleted by Rev. 23.
- e. The NRC Operations Office will be notified by the appropriate Emergency Communicator within one hour, using an NRC Event Notification Worksheet approved by the SEC.
Plant personnel designated on the Emergency Response Organization
.are notified of an emergency condition by the Emergency Communicator using a computer-based automated duty roster system, or as a backup, a system of pagers and telephone call trees.
These personnel are requested to be available on site to respond as directed by the Site Emergency Coordinator.
ge Personnel on site are notified by the Main Control Room using a plant Public-Address System announcement that an emergency has been declared and what actions should be taken.
Corporate personnel on the Emergency Response Organization will be notified of an emergency at HNP in accordance with plant emergency procedures.
The off-site agencies that will be notified of an emergency condition at HNP are shown in Tables 4.2-1 through 4.2-4.
3 ~ Notifications to off-site agencies shall include a means of verification or authentication such as the use of dedicated communications networks, verification code words, or providing callback verification phone numbers.
4.3 Activation Facilities are to be activated for each emergency class in accordance with Tables 4.2-1 through 4.2-4.
- b. The Communications Director will verify the readiness and operability of emergency facilities in the Technical Support Center (TSC) and the Administrative and Logistics Manager will verify the readiness and operability of the Emergency Operations Facility (EOF).
PLP-201 Rev. 26 Page 58 of 131
4.3 Activation (continued)
The Emergency Repair Director will verify the readiness of the Operational Support Center.
- d. The JIC Director will verify the readiness of the Joint Information Center.
Security measures will be established for the Emergency Operations Facility upon its activation.
Personnel in the Emergency Response Organization will report to their preassigned locations in the emergency facilities.
g The individual to assume the position of Site Emergency Coordinator in the Technical Support Center will report to the TSC before the TSC is activated. He may activate the TSC before all of his staff (such as, Plant Operations Director, Technical Analysis Director, Radiological Control Director, Communications Director) are present, but for those staff members not present, he must assume their duties or assign their duties to a qualified individual.
4.4 Assessment Actions 4.4 ' Evaluation of Plant Conditions a Evaluation of plant conditions by Operations personnel is accomplished thx'ough observation of the control boards, monitoring panels, ERFIS data displays, the SPDS displays, and information provided by the Accident Assessment Team.
The Accident Assessment Team evaluates plant conditions from the Technical Support Center using ERFIS displays, damage assessment reports, seismic data, fire reports, dose projections, and monitoring data.'ore damage assessment methodology is applied by the Accident Assessment Team utilizing data provided from the ERFIS, the Control Room, the Radiation Monitoring System, and the Chemistry Team.
4.4.2 Plant Radiolo ical Monitorin The Radiation Monitoring System (RMS) will be used by Operations personnel and Radiological Control Team members to determine high radiation areas within the plant or abnormal radioactive effluents.
The Radiological Control Team will provide in-plant radiological measurements to supplement and confirm the RMS.
The Primary Sampling System may be used by the Chemistry Teams, where possible, to provide radiochemistxy samples for analysis.
The Post Accident Sampling System provides the capability to sample reactor coolant and the containment atmosphere. Highly radioactive samples can be proportionally diluted by this system for later analysis. The Post Accident Sampling System will be operated by the Chemistxy Team.
PLP-201 Rev. 26 Page 59 of 131
e 4.4.3 Dose Pro'ection Dose projections will be made to determine the off-site doses that might result from an accident and the possible need for protective action (see Table 4.5.1 and Annex B).
The dose projection capability on the computer can use source term data from the Radiation Monitoring System, and meteorological data from the on-site meteorological station. This system will aide personnel in the Main Control Room or EOF in determining recommendations for protective action for the public.
Data from the Radiation Monitoring System that is used to determine the source term for dose projections is quality tagged.
If the data is off-scale, then it is suspect or bad, and the effluent radiation levels must be determined by sampling at the radiation monitor test points. The results from analyzing the samples can be entered into the dose projection program as a substitute value.
Radionuclide mix assumptions in Annex B (the accident source term) are contained in the computerized dose projection program as default values for use until actual sampling data can be substituted.
The Weather Center will be contacted as needed to forecast atmospheric conditions affecting the site.
4.4.4 Environmental Monitorin a Deleted by Revision 23.
- b. Environmental sampling and monitoring points are specified in environmental monitoring procedures.
Environmental Monitoring Teams will be activated in accordance with Table 2.2-1 and appropriate PEPs. Additional teams can be called upon for support as needed.
The Environmental Monitoring Teams will track the plume from any radiological release by monitoring radiation levels as indicated on radiological measuring instruments and by obtaining and analyzing air samples.
The Environmental Monitoring Teams will aid in assessing liquid release pathways by sampling liquid effluents, such as the cooling tower blowdown.
Additional TLDs will be placed at various locations near the site and be periodically replaced throughout an emergency to ensure that a cumulative dose record is obtained.
4.5 Protective Actions for the Public 4.5.1 Protective Action Guides a ~ For incidents involving actual or imminent releases of radioactive material to the atmosphere or loss of control of the plant, protective action recommendations will be based upon NRC RTM-92 methodology and the EPA protective action guidelines indicated in Table 4.5-1, as implemented by PEP-104.
PLP-201 Rev. 26 Page 60 of 131
Y 4.5.1 Protective Action Guide (continued)
- b. For incidents involving contamination of food, water, or milk, protective action recommendations will be consistent with the guidance of EPA-400-R-92-001. The EPA guidance is summarized in Table 4.5-2.
4.5.2 CP&L Recommendations to Local Authorities The decision to implement protective actions for the off-site population at risk is the responsibility of the state and local governments. Detailed procedures for public protective actions are contained in the North Carolina Emergency Response Plan in Support of the Harris Nuclear Power Plant.
All sectors that are not recommended to evacuate will be recommended to shelter. The State may consider sheltering for doses up to 5 rem TEDE for hazardous environmental conditions, and for doses up to 10 rem TEDE for special populations. Special populations may include institutionalized or infirm persons. Hazardous environmental conditions may include the presence of severe weather or competing disasters.
The local housing consists primarily of one- and two-story wood-framed dwellings. Very few houses have basements. There are a number of brick or brick veneer dwellings of later construction and several parks of house trailers. The representative protection factors for surface deposited radionuclides and for a gamma cloud source are, respectively, for wood frame houses with no basements (2.5 and 1.1) and for masonry houses with no basement (5 and 1.7).
At a General Emergency classification, Carolina Power & Light Company will provide the state and local governments with recommendations for protective actions for the public based on the guidance contained in PEP-104.
4.5.3 Public Alertin , Warnin , and Notification Alerting, warning, and notification of the public are steps taken by government agencies to advise the public that protective actions are necessary. Alerting, warning, and notification will be provided by sounding sirens, activation of tone-activated radios within five miles of the plant, and supplemented by announcements made through radio and television (EAS),
sound trucks, bullhorns, and knocking on doors. Patrol boats will be used in alerting people on Lake Jordan and Harris Lake in accordance the North Carolina Emergency Response Plan in support of the Shearon Harris Nuclear Power Plant Annexes G & J. Supplemental sirens are provided for alerting boaters on Harris Lake. Public warning when deemed necessary will be accomplished as described in the North Carolina Emergency Response Plan in Support of the Shearon Harris Nuclear Power Plant. Preplanned emergency messages and emergency instructions have been prepared and included as Annex D to that plan.
Civil defense sirens mounted on 50-foot utility poles have been installed by Carolina Power & Light Company at various locations within a 10-mile radius of the HNP.
PLP-201 Rev. 26 Page 61 of 131
4.5.3 Public Alertin , Warnin , and Notification (continued)
Activation of the sirens and tone alert radios for warning of the public will be accomplished from the county Warning Points or county Emergency Operations Centers: the Public Safety Communications Centers of Harnett and Lee Counties, the Emergency Operations Center of Chatham County, and the Raleigh Communications Center for Wake County. The sirens in each county are independently controlled by radio. The outdoor warning system provides the capability for providing an alerting signal within the 10-mile EPZ, within 15 minutes from the time the decision is made to notify the public of an emergency situation. The tone alert radios provide an indoor alerting signal within a 5-mile radius of the plant.
4.6 Protective Actions for On-Site Personnel 4.6.1 On-Site Alertin , Warnin , and Notification The Plant Public-Address (PA) System will be used to alert and notify on-site personnel of an emergency condition within 15 minutes. Security personnel with portable loudspeakers may be used to augment the PA System and/or check evacuation of outlying areas, as available. The Plant PA System has the capability to transmit recognizable alarms which will alert personnel of an emergency situation, and to transmit voice communications which will notify personnel of those actions which should be taken. The Plant PA System is supplemented by the use of the normal and emergency communication systems located on site as described in Section 3.8 of this Plan.
4.6.2 Evacuation and Personnel Accountabilit All personnel on-site will be accounted for within 30 minutes of the declaration of a Site Emergency or General Emergency and continuously thereafter during the emergency (accountability may be accomplished at any time prior to the declaration of a Site Emergency, upon notification to do so by the Site Emergency Coordinator) . Designated personnel in the assembly areas will perform personnel accountability functions and report missing persons to Security. Continuous accountability of personnel remaining in the plant will be performed by the designated team leaders and managers among the represented disciplines. Plant Emergency Procedure PEP-382, Personnel Accountability, describes the accountability methodology. Search procedures will be implemented to locate unaccounted for persons.
Evacuation of on-site personnel can be accomplished, in accordance with plant emergency procedure PEP-381, for the Site or the Exclusion Area.
a 0 A Site Evacuation involves evacuation of all nonessential personnel within the Protected Area, Admin Building, parking lots, cooling tower area, sewage treatment plant, landfill, and intake structures. The site evacuation alarm will be sounded on the Plant PA system. Nonessential personnel (that is, CP&L personnel not on the ERO, ERO personnel not assigned to emergency duties and contractors) within the Protected Area will normally exit the Protected Area via the security building in accordance with normal Security procedures. Evacuating personnel may be monitored for contamination by the portal monitors as they exit the Protected Area or with portable friskers in the evacuation monitoring area, based on the situation. ERO personnel not assigned to emergency duties will travel to the HE&EC auditorium. CP&L personnel not on the ERO and contractors shall depart the site using personal transportation and follow established evacuation routes.
Personnel without transportation will arrange for a ride from others who have space in their vehicles.
PLP-201 Rev. 26 Page 62 of 131
4.6.2 Evacuation and Personnel Accountibilit (continued)
Nonessential personnel exiting the site will be directed to either proceed to their homes or if radiological conditions warrant, reassemble at a selected off-site assembly area until off-site monitoring and decontamination stations are in place. Personnel exiting evacuated areas will be monitored and decontaminated, necessary, at county monitoring stations.
if
- b. An Exclusion Area Evacuation involves evacuation of all nonessential personnel and the public within the Protected Area and the site, as well as the surrounding areas controlled by CP&L within the Exclusion Area Boundary. In addition to sounding the plant evacuation alarm, personnel in outlying areas can be notified by patrol vehicles. If conditions warrant, evacuating personnel will be instructed to reassemble at the selected remote assembly area until county monitoring and decontamination stations are established.
c Local evacuations relating to Radiation Control Areas and fire protection are conducted in accordance with plant procedures.
4.6.3 Radiolo ical Ex osure Control 4.6.3.1 Radiolo ical and Contamination Control Facilities Radiation safety controls are established 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day to contain the spread of loose surface radioactive contamination and monitor personnel exposure. CP&L radiation and contamination control limits are shown in Table 4.6-1. Emergency exposure guidance is given in Section 4.6.3.4 of this plan. The radiation control facilities located in the Waste Processing Building include a contaminated laundry and storage area, clean laundry and storage area, personnel and equipment decontamination area. Additional areas where equipment is decontaminated are located in the Reactor Auxiliary Building (on the 236'nd 261'evels) and at the north end of the Fuel Handling Building (on the 261'evel). Radiation control and radiation control pro'cedures are described in Section 12.5 of the FSAR.
Temporary facilities to limit contamination and exposure will be established as necessary during an emergency situation. As an example, facilities which can be used for personnel decontamination during an emergency are located near the first aid room in the Turbine Building and at the Harris Energy &
Environmental Center. Radiation Control Areas can be expanded by roping off areas and/or establishing access control points to maintain personnel exposure As Low As Reasonably Achievable (ALMA.).
4.6.3.2 Ex osure Records for Emer enc Workers Emergency workers will receive self reading pocket dosimeters (SRPDs) or equivalent and TLD badges. Dose records will be maintained by the Radiological Control Coordinator in accordance with PEP-371.
4.6.3.3 Use of Protective E ui ment and Su lies During the course of an emergency, protective actions will be considered to minimize the effects of radiological exposures or contamination problems associated with personnel who must work within the affected Radiation Control Area. Measures that will be considered are:
Use of process oz engineering controls; Distribution of respirators; PLP-201 Rev. 26 Page 63 of 131
4.6.3.3 Use of Protective E ui ment and Su lies (continued)
- Use of protective clothing; and
- Use of thyroid blocking agents (Potassium Iodide).
The criteria for issuance of respiratory protection and protective clothing are described in plant radiological protection procedures.
Procedures for the administration of radioprotective drugs to employees aze described in the plant emergency procedures.
4.6.3.4 Emer enc Worker Ex osures Durin Lifesavin and Re air/Reentr Efforts Dose Limits for workers in an emergency are taken from EPA 400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, " U.S. Environmental Protection Agency, May 1992. Much of the discussion in this section is taken in whole from that document.
In emergency situations, workers may receive exposure under a variety of circumstances in order to assure protection of others and of valuable property. These exposures will be justified if the maximum risks or costs to others that are avoided by their actions outweigh the risks to which the workers are subjected.
The Emergency Worker Dose Limits are as follows:
Dose Limit (rem TEDE) Activity Condition 10 Protecting valuable ro ert Lower dose not racticable 25 Lifesaving or protection of Lower dose not practicable lar e po ulations 25 Lifesaving or protection of Only on a voluntary basis to large populations persons fully aware of the risks involved.
Limit dose to the lens of the eye to three (3) times the above values and doses to any other organ (including skin and body extremities) to ten (10) times the above values.
Routine dose limits shall not be extended to emergency dose limits for declared pregnant individuals. As in the case of normal occupational exposure, doses received under emergency conditions should be maintained as low as reasonably achievable.
In the context of these limits, exposure of workers that is incurred for the protection of large populations may be considered justified for situations in which the collective dose avoided by the emergency operation is significantly larger than that incurred by the workers involved.
Persons undertaking any emergency operation in which the dose will exceed 25 rem TEDE should do so only on a voluntary basis and with full awareness of the risks involved including the numerical levels of dose at which acute effects of radiation will be incurred and numerical estimates of the risk of delayed effects.
PLP-201 Rev. 26 Page 64 of 131
4.6.3.4 Emer enc Worker Ex osure Durin Lifesavin and Re air/Reentr Efforts (continued)
Planned exposures shall not exceed 75 rem TEDE.
The personnel who will perform planned actions should be determined in accordance with guidelines contained in PEP-371.
Entry into radiation fields of greater than 25 rem/hour or planned exposures in excess of 5 rem TEDE shall not be permitted unless specifically authorized by the Site Emergency Coordinator for on-site emergency workers and by the Emergency Response Manager for EOF or EOF dispatched personnel.
4.6.3.5 Deleted 4.6.3.6 Decontamination and First Aid 4.6.3.6.1 Treatment of In'ured and Contaminated Persons Personnel decontamination supplies are located in the First Aid Room. Personnel showers are located in the general area of the main RCA entrance (WPB 261'). Chemical decontamination agents are available from Health Physics personnel and, except in cases of severe or life-threatening injury, established decontamination procedures should be employed on site prior to medical treatment.
- 4. 6. 3. 6. 2 Initial First Aid In cases of severe injury, lifesaving first aid or medical treatment wi11 take precedence over personnel decontamination. In general, the order of medical treatment will be:
Care of. severe physical injuries or illness.
- Personnel decontamination.
- First aid to other injuries.
Definitive medical treatment and subsequent therapy as required.
Definitive medical treatment, therapy, and evaluation may include radioprotective drugs, urinary bioassays, or whole body counts on persons suspected of inhaling or ingesting a significant amount of radioactive material or may include surveillance and therapy for persons receiving a large whole body dose.
Emergency first aid personnel, trained in Standard First Aid and CPR in accordance with the American Red Cross standards, are available on all shifts.
Personnel who are contaminated and who require medical treatment may be treated by these personnel on the scene, in the plant's First Aid Room located in the Turbine Building or at other appropriate locations. Figure 1.5-3 depicts the location of First Aid room.
It is anticipated that contaminated personnel will not leave the facility for medical treatment except for cases that require immediate hospitalization.
Emergency medical treatment of contaminated personnel will normally be handled at the plant First Aid Room by personnel on the First Aid Team(s).
PLP-201 Rev. 26 Page 65 of 131
4.6.3.6.2 Initial First Aid (continued)
First Aid kits are located in the facilities listed in Table 3.1-1 (excluding the Joint Information Center) and contain simple board splints, roller bandages, gauze compresses, triangular bandages, and blankets. The First Aid Room contains first aid kits and the following additional equipment that is used by personnel with advanced training, when such personnel are available:
- Oxygen resuscitator
- Eye care kit
- Blood pressure cuff and stethoscope
- Obstetrics kit
- Air splints Ring cutter 4.6.3.6.3 Decontamination Radiation safety controls are established to contain the spread of loose surface radioactive contamination. Personnel and equipment-leaving contaminated areas are monitored to ensure that equipment, personnel or their clothing are not contaminated. If contaminated above acceptable levels (see Table 4.6-1), they will be decontaminated in accordance with plant procedures.
Supplies, instruments and equipment that are in contaminated areas or have been brought into contaminated areas will be monitored for contamination.
found to be contaminated, they will be decontaminated using normal plant If decontamination techniques and facilities (discussed in Section 4.6.3.1) or may be disposed of as radwaste.
During emergency conditions, normal plant contamination control criteria will be adhered to as much as possible. Contamination control criteria for returning areas and items to normal use are contained in the plant Health Physics Procedures. These criteria are summarized in Table 4.6-1.
4.6.3.6.4 Medical Trans ortation The Apex Volunteer Rescue Squad has agreed to respond to emergency calls from the plant, including transporting persons with injuries involving radioactive contamination. This service is available on a 24-hour-per-day basis. In cases not involving severe injury, one of the plant vehicles may be used to transport injured individuals. The Apex Volunteer Rescue Squad is included in Annex A, "Agreements".
In cases involving severe injury, the Superintendent Shift Operations or Site Emergency Coordinator may bypass the Apex Volunteer Rescue Squad and directly call Carolina Air Care or Duke Life Flight and request helicopter transport of the injured.
Contaminated injured persons will be accompanied to a medical facility by a Radiological Control Team member with an appropriate survey instrument. If possible, contaminated clothing and equipment may be removed from the patient or the patient may be wrapped in clean sheets or clothing to prevent contamination of the transporting personnel and vehicle.
Rescue vehicles have mobile communications with the Raleigh Communications Center and local receiving hospitals. The plant first aid team can communicate directly with the rescue vehicles by dialing the cellular'hone located in the rescue vehicles.
PLP-201 Rev. 26 Page 66 of 131
4.6.3.7 Medical Treatment 4.6.3.7.1 Hos ital Facilities A specially designated emergency area is maintained in readiness at Rex Hospital for CP&L's use for the treatment of contaminated or overexposed patients from the plant. Although this area will be utilized by the hospital when not requized by CP&L, it will be made available to CP&L when required.
Equipment is available in the hospital for the emergency treatment of patients. With the facilities and equipment available, extensive decontamination and treatment of an injured patient could be performed, including any surgical treatment that may be required.
Wake Medical Center and Western Wake Medical Center serve as backup medical facilities foz HNP personnel should Rex Hospital become unavailable. Wake Medical Center serves as the primary medical facility for trauma patients from HNP. Wake Medical Center, Betsy Johnson Memorial Hospital, in Dunn, N.C., and Central Carolina Hospital, in Sanfordg NUCLEI also possess the capability foz the treatment of contaminated and/or overexposed members of the public in Wake County.
An emergency kit is maintained at Rex Hospital, Wake Medical Center and Western Wake Medical Center containing supplies and equipment for personnel monitoring and the control of radioactive contamination. These kits contain the following:
Low-range radiation monitoring instruments for determining contamination levels.
Personnel monitoring equipment such as self-reading pocket dosimeters and TLDs.
Decontamination equipment and supplies for both personnel and facility.
Contamination control equipment and supplies such as protective clothing, signs, ropes, tags, plastic bags.
Agreements with Rex Hospital, Wake Medical Center and Western Wake Medical Center aze maintained on file by HNP Emergency Preparedness. These three hospitals are listed in Annex A, "Agreements".
4.6.3.7.2 Medical Consultants Medical assistance is available in the Raleigh area from general practitioners who have agreed to provide medical assistance for contaminated patients (See Annex A). Also, the U.S. Department of Energy Radiological Assistance Team will provide medical assistance, if required.
PLP-201 Rev. 26 Page 67 of 131
4.6.3.8 Contamination Control of Drinkin Water and Food Measures will be taken to control access to potentially contaminated potable water and food supplies on site. Under emergency conditions when uncontrolled releases of activity have occurred, eating, drinking, smoking, and chewing will be not permitted until the Site Emergency Coordinator has determined that it is safe to do so. If the water is contaminated above acceptable drinking water levels, uncontaminated water will be brought into the plant for the emergency workers to drink. Emerg'ency food supplies are stored in a secure manner (See Table 3.1-1). Packaged food is located in vending machines in lunch rooms or office areas in the Administration Building, Fuel Handling Building "K" area, Operations Building, or Service Building. If these areas become contaminated because of a release of activity, the machines will be disabled or emptied until it can be verified that the food is not contaminated or the food will be discarded. Food located in the Service Building cafeteria is stored in refrigerators or boxes and would be verified uncontaminated prior to use.
4.7 Fire-Fi htin Assistance Off-site fire departments will provide support as described in Annex A and Annex G.
4.8 Securit Measures Security measures during an emergency will be employed in accordance with the Plant Security Plan, implementing Security procedures, and Plant Emergency Procedures dealing with personnel accountability; egress, and ingress, PLP-201 Rev. 26 Page 68 o f 131
TABLE 4.0-1 Off-Site A enc Su ort Summar Function (NUREG-0654, II.A) primer Res onsinilit ~sn ort Command and Control a ~ On site HNP CP&L
- b. Off site State, County FEMA
- 2. Accident Classification a ~ On site HNP N/A
- b. Off site N/A N/A
- 3. W~arnin
- a. On site HNP N/A
- b. Off site HNP State, County, Media
- 5. Notification, Public
- a. On site (such as Visitors) HNP N/A
- b. Off site State, County Telephone Company, CP&L Trans ortation a ~ On site HNP/Employees N/A Off site Local Residents County, State
- 8. Traffic Control/Securit a ~ On site HNP County
- 10. Public Information/Education
- a. On site HNP, Corp. Comm. NRC
- b. Off site State County, Corp.
Comm., Media, FEMA PLP-201 Rev. 26 Page 69 of 131
TABLE 4.0-1 Off-Site A enc Su ort Summar (continued)
Function (NUREG-0654, ZZ.A) Primer Res onsinilit ~su ort
- 11. Protective Res onse
- 12. Radiolo ical Ex osure Control
- 13. Fire and Rescue
- a. On site HNP Local Fire Rescue
- b. Off site County State
- 14. Medical
- a. On site HNP Rescue, Hospital
- b. Off site County State
- 15. Public Health & Sanitation
- a. On site HNP N/A
- b. Off site County State
- 16. Social Services a ~ On site N/A N/A
- b. Off site County State
- 17. ~Trainin
- 18. Exercises
- b. Off site State County, CP&L
- 19. ~Reentr
CPCL Carolina Power a Light Company NRC U.S. Nuclear Regulatory Commission DHHS U.S. Department of Health a Human Services HNP Harris Nuclear Plant DOE U.S. Department of Energy W Westinghouse Electric Corporation Ebasco Ebasco Services, Inc. N/A Not applicable fEMA U.S. federal Energy Management Agency PLP-201 Rev. 26 Page 70 of 131
TABLE 4.2-1 A.
This class involves events which indicate a potential degradation of the level of safety at a nuclear station.
No releases of radioactive material requiring off-site response or monitoring are expected unless further degradation of safety systems occurs.
C. 'QIIEQ Time frames noted below are from the time the emergency is declared.
'tate of North Carolina Emergency Warning Point (fifteen minutes)
'hatham County Emergency Warning Point (fifteen minutes)
'arnett County Emergency Warning Point (fifteen minutes)
'ee County Emergency Warning point (fifteen minutes)
'ake County Emergency Warning Point (fifteen minutes)
'n-site Emergency Response Organization (as specified by procedure)
'ff-site Emergency Response Organization (as specified by procedure)
'uclear Regulatory Commission Operations Center (one hour)
'basco,lnc.
'estinghouse Electric Corporation
'nstitute of Nuclear Power Operations
'merican Nuclear Insurers
'uclear Mutual Limited (Fire Only)
'epartment of Energy, Savannah River Operations Office D.
" On-site Emergency Response Organization (not required, but should be done as necessary)
Technical Support Center Operational Support Center
'ff-site Emergency Response Organization (not required, but should be done as necessary)
Emergency Operations Facility, Joint Information Center
'equest Assistance (if necessary)
Rex Hospital Wake Medical Center Western Wake Medical Center Fire and Rescue Departments PLP-201 Rev. 26 Page 71 of 131
TABLE 4.2-2 A.
This class describes events which involve actual or potential substantial degradation of the level of safety at a nuclear station.
Off-site doses expected to be limited to small fractions of EPA Protective Action Guideline exposure levels.
C. HOIlEY.:
Time frames noted below are from the time the emergency is declared.
'tate of North Carolina Emergency Warning Point (Fifteen minutes)
'hatham County Emergency Warning Point (Fifteen minutes)
'arnett County Emergency Warning Point (Fifteen minutes)
'ee County Emergency Warning Point (Fifteen minutes)
'ake County Emergency Warning Point (Fifteen minutes)
'n-site Emergency Response Organization
'ff-site Emergency Response Organization
" Nuclear Regulatory Commission Operations Center {One hour)
'merican Nuclear Insurers (Four hours)
'uclear Mutual Limited {Fire only)
'nstitute of Nuclear Power Operations {Four hours)
'basco,lnc.
'estinghouse Electric Corporation
'epartment of Energy, Savannah River Operations Office D.
'n-site Emergency Response Organization:
Technical Support Center Operational Support Center
'ff-site Emergency Response Organization Emergency Operations Facility Joint Information Center (not required, but should be done as necessary)
'equest Assistance if necessary:
Rex Hospital Wake Medical Center Western Wake Medical Center Fire and Rescue Departments PLP-201 Rev. 26 Page 72 of 131
TABLE 4.2-3 A.
This class describes events which involve major failures of plant functions needed for the protection of the public.
Off-site doses not expected to exceed EPA Protective Action Guidelines exposure levels except near site boundary.
C. blQIIEY:
Time frames noted below are from the time the emergency is declared.
'tate of North Carolina Emergency Warning Point (Fifteen minutes)
'hatham County Emergency Warning Point (Fifteen minutes)
'arnett County Emergency Warning Point (Fifteen minutes)
'ee County Emergency Warning Point (Fifteen minutes)
'ake County Emergency Warning Point (Fifteen minutes)
'n-site Emergency Response Organization
'ff-site Emergency Response Organization
'uclear Regulatory Commission Operations Center (One hour)
'merican Nuclear Insurers (Four hours)
'uclear Mutual Limited (Fire Only)
'nstitute of Nuclear Power Operations (Four hours)
'basco,lnc.
" Westinghouse Electric Corporation
'epartment of Energy, Savannah River Operations Office D.
'n-site Emergency Response Organization Technical Support Center Operational Support Center
'ff-site Emergency Response Organization Emergency Operations Facility Joint Information Center
'equest Assistance (if necessary)
Rex Hospital Wake Medical Center Western Wake Medical Center Fire and Rescue Departments PLP-201 Rev. 26 Page 73 of 131
TABLE 4.2-4 A.
This class involves events which involve actual or imminent substantial core degradation or melting with the likelihood of a related release of appreciable quantities of fission products to the environment.
Doses expected to be greater than the upper EPA Protective Action Guideline exposure levels off-site for more than the immediate site area.
C. blQIIEY.:
Time frames noted below are from the time the emergency is declared.
State of North Carolina Emergency Warning Point (Fifteen minutes)
Chatham County Emergency Warning Point (Fifteen minutes)
Harnett County Emergency Warning Point (Fifteen minutes)
Lee County Emergency Warning Point (Fifteen minutes)
Wake County Emergency Warning Point (Fifteen minutes)
On-site Emergency Response Organization Off-site Emergency Response Organization Nuclear Regulatory Commission Operations Center (One hour)
American Nuclear Insurers (Four hours)
Nuclear Mutual Limited (Fire only)
Institute of Nuclear Power Operations (Four hours)
Ebasco,lnc.
Westinghouse Electric Corporation Department of Eneigy, Savannah River Operations Office D.
'n-site Emergency Response Organization:
Technical Support Center Operational Support Center
'ff-site Emergency Response Organization:
Emergency Ope'rations Facility Joint Information Center
'equest Assistance (if necessary)
Rex Hospital Wake Medical Center Western Wake Medical Center Fire and Rescue Departments PLP-201 Rev. 26 Page 74 of 131
e TABLE 4.5-1 Protective Action PAG Comments Evacuate 1 rem [TEDE[ Change any sheltering subzones/sectors to evacuate if [Total Effective Dose Equivalent) dose within any area exceeds PAG.
Evacuate 5 rem [CDE[ Change any sheltering subzones/sectors to evacuate if
[Committed Dose Equivalent[ dose to the thyroid within any area exceeds PAG.
[
Reference:
EPA 400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," U.S. Environmental Protection Agency, Washington, D.C., May 1992.]
PLP-201 Rev. 26 Page 75 of 131
TABLE 4.5-2 Projected Dose Commitment to Protective Whole Body, Bone Marrow or any Projected Dose Commitment to Action other Organ (rem) the Thyroid (rem)
Preventive 1.5 Emergency PAG~ 1 5.0 5.0
" Preventive PAG- The projected dose commitment value at which responsible officials should take protective actions having minimal impact to prevent or reduce the radioactive contamination of human food or animal feed.
~'mergency PAG- The projected dose commitment value at which responsible officials should isolate food containing radioactivity to prevent its introduction into commerce and at which the responsible officials should determine whether condemnation or other disposition is appropriate.
From: *"
Contamination of Human Food and Animal Feeds, Recommendations for State and Local
'""'i'"***'"'adioactive Agencies PLP-201 Rev. 26 Page 76 of 131
Table 4.6-1
- 1. Radiation Area 5 to s100 mrem/hr
- 2. High Radiation Area >100 mrem/hr to c 1000 mrem/hr
- 3. Locked High Radiation Area 1000 mrem/hr to c 500 rad/hr
- 4. Very High Radiation Area > 500 rad/hr 5 1 meter
- 5. Airborne Radioactivity Area Airborne Conc. z 25% of 10CFR20, App. B, Table 1 Column 3 Skin contamination or personal < 100 net cpm ()y with HP210 clothing probe or equivalent sensitivity no measurable a count rate above background Unconditional release from site No detectable a and for tools and equipment
< 100 net cpm ()y with HP210 probe or equivalent sensitivity
- 3. Contamination Area > 1000 dpm/100cm')y smearable and/or > 20 dpm/100cm'a
- 4. High Contamination Area > 50,000 dpm/100cm')y smearable and/or > 1000 dpm/100cm'
Planned Personnel Exposure 75 rem TEDE (1) Planned Personnel exposures greater than 5 rem TEDE are not permitted unless specifically authorized by the Site Emergency Coordinator (on-site personnel) or Emergency Response Manager (off-site CP8 L personnel).
PLP-201 Rev. 26 Page 77 of 131
Figure 4.1-1 Emergency Action Level Flow Path, Side 1 Folded copy of Emergency Action Level Flowpath, Side 1, (Rev. 96-1) is contained in the lastic sleeve following this pa e.
PLP-201 Rev. 26 Page 78 of 131
Figure 4.1-2 Emergency Action Level Flow Path, Side 2 Folded copy of Emergency Action Level Flowpath, Side 2 (Rev. 96-1) is contained in the plastic sleeve following this page.
PLP"201 Rev. 26 Page 79 of 131
5.0 MAINTAINING EMERGENCY PREPAREDNESS
= Emergency preparedness at HNP will be maintained by:
'a 0 Maintaining planning documents through review, updates, audits, and annual PNSC review.
- b. Preparing Emergency Response Organization members for proper response actions through training and retraining.
Testing the adequacy of emergency preparedness through the use of drills and exercises.
Inventorying and calibrating emergency equipment, supplies, and instrumentation.
Each periodic requirement in this section and elsewhere in the plan and plant emergency procedures shall be performed within the specified time below:
- a. Annually At least once per 366 days
- b. Monthly At least once per 31 days
- c. Quarterly At least once per 92 days
- d. Semiannually- At least once per 184 days For the above intervals, a maximum allowable extension which shall not exceed 25% of the specified interval is allowable.
This definition for periodic requirements applies to all intervals in the emergency plan and plant emergency procedures except for the annual exercise, which is conducted once per calendar year.
5.1 Emer enc Plan and Plant Emer enc Procedures 5.1.1 Res onsibilit for the Plannin Effort The HNP Emergency Planning Coordinator is responsible for coordinating on-site and selected off-site radiological emergency response planning. He is also responsible for 'performing the following planning functions:
a Interfacing with federal, state, county, and local planners.
Revising and updating the Plan in response to action items identified during appraisals, audits, exercises, drills, and changes in regulations, hardware, and personnel.
Coordinating the annual exercise and the periodic drills.
Identifying off-site training needs of state and local emergency support personnel and arranging for training to meet the identified needs.
- e. Identifying corrective actions needed following drills and exercises, appraisals, and audits; coordinating responsibility for implementing these actions; coordinating a schedule for completion of these actions; and evaluating the adequacy of the actions taken.
Maintaining and negotiating agreements with state and county response agencies, federal assistance agencies, and medical and fire support agencies.
PLP-201 Rev. 26 Page 80 of 131
5.1.2 Emer enc Plan and Plant Emer enc Procedures U date and Chan es The Emergency Planning coordinator will coordinate the updating of the Plant Emergency Plan, Plant Emergency Procedures, and Supporting Agreements as needed and will review and certify them to be current on an annual basis. The EALs shall be approved by the State of North Carolina and Wake, Chatham, Harnett,,and Lee Counties annually. Plan and Procedure revisions shall be reviewed and,'approved in accordance with an approved plant procedure.
Approved changes to the Plan will be distributed in accordance with the distribution list for the plan and procedures in a plant procedure. Revised pages will be indicated in accordance with plant procedures.
Changes to the E-Plan or PEPs shall be forwarded to the NRC within 30: days after approval.
5.1.3 U datin Tele hone Listin s Updating of emergency phone listings or personnel listings is not a change to the Plan. Emergency phone listings and personnel listings shall be updated at least quarterly.
I 5.1.4 Plant Emer enc Procedures A list of Plant Emergency Procedures required to implement this Plan is provided in Annex E.
5.1.5 NUREG-0654 Cross-Reference The criteria for radiological emergency response plans contained in NUREG-0654 are cross-referenced to the applicable sections of this Plan and supporting Plans in Annex D.
5.1.6 Annual Inde endent Audit An independent audit of the HNP Emergency Preparedness Program will be conducted every year by the Nuclear Assessment Section. The Nuclear Assessment Section will audit the Plan, Plant Emergency Procedures, Training, Drills and Exercise, facilities and equipment for conformance with 10CFR50.47, 10CFR50.54, and 10CFR50 Appendix E. Written reports of the findings of these audits and reviews will be provided to Corporate Management. Written notification will be provided to the State of North Carolina and Counties of Chatham, Harnett, Lee, and Wake of the performance of the audit and the availability of the audit records for review CPaL facilities. Each report will address the adequacy of interfaces with at state and local governments, of drills and exercises, and of emergency response capabilities and procedures.
The reports will be retained by Emergency Preparedness for five years.
Corrective actions deemed necessary from the audit will be implemented in accordance with Section 5.1.1.e of this Plan and the site Corrective Action Program.
5.2 Emer enc Plan Trainin Pro ram 5.2.1 General Re uirements The Emergency Plan Training Program assures training of individuals who may be called on to assist in an emergency. Initial training and annual retraining is provided. Responsibilities for implementing the Training Program are contained in PEP-403, and a description of the content of training courses is described in TPP-203, "Emergency Preparedness Training Program", FPP-016, "Fire Protection and First Aid Training" and SP-004, "Security Orientation, Indoctrination, and Training".
PLP-201 Rev. 26 Page 81 of 131
5.2.1 General Re uirements (continued)
ERO personnel assigned to on-site and off-site CP&L emergency facilities (excluding the Joint Information Center) are required to receive Radiation Worker Training initially and on an annual basis.
The initial training and qualification program for members of the CP&L Emergency Response Organization filling Key Positions, as defined in PEP-407, includes drill performance during which each individual demonstrates the ability to perform assigned emergency functions as witnessed by another person qualified in the same position, by a person in the ERO to whom that person reports, or to a member of the Emergency Preparedness staff. On-the-spot correction of erroneous performance will be made and a demonstration of proper performance offered by the evaluator.
Training for individuals assigned to First Aid Teams will include courses equivalent to the Red Cross Multimedia First Aid Course.
Designated individuals, as shown on the ERO Roster, are also required to be qualified in the use of appropriate respiratory protection equipment.
Training is provided for the following categories of personnel:
Directors, Coordinators, and Managers in the Emergency Response Organization.
- b. Personnel responsible for accident assessment.
C, Radiological monitoring teams and radiological analysis personnel.
Police, security, and off-site fire-fighting personnel.
Damage Control Teams First Aid, Search and Rescue, and Fire Brigade personnel.
ge Local support services personnel, including emergency management personnel.
Medical support personnel.
Personnel responsible for transmission of emergency information and instructions.
Personnel responsible for communicating with the media and public.
5.2.2 Moved to 5.2.1.). by Revision 25.
PLP-201 Rev. 26 Page 82 of 131
5.2.3 Off-site Or anizations Training of off-site organizations is described in their respective radiological emergency plans. Additional training is provided by CP&L for hospital, rescue, local law enforcement agencies, and fire personnel. Such training will include the procedures for notification, basic radiation protection, and their, expected roles. For those Immediate Response Organizations who may enter the site, training by CP&L will also include site access procedures and the identity (by position and title) of the individual in the HNP organization who will control the organization's support activities. CP&L will assist these off-site organizations in performing their radiological emergency response training as related to HNP as requested.
Training of medical support personnel at the agreement hospitals will include basic training on the nature of radiological emergencies, diagnosis and treatment, and follow-up medical care.
5.2.4 Emer enc Plannin Coordinator and Staff Trainin Training of plant emergency preparedness personnel involved in the planning effort will consist of the following:
- a. Observing exercises in other plants
- b. Participation in emergency preparedness workshops, seminars and/or courses 5.2.5 Public Education and Information CP&L Occupants in the Plume Exposure Pathway Emergency Planning Zone (EPZ) will be provided information prepared by CP&L in conjunction with the state and county agencies. This public education and information program is intended to ensure that members of the public are (1) aware of the potential for an occurrence of a radiological emergency; (2) able to recognize a radiological emergency notification; and (3) knowledgeable of the proper, immediate actions to be taken upon notification.
This will be accomplished by (1) distribution of the annual safety information calendar which contains educational information on emergency preparedness, sheltering, sirens, and radiation including telephone numbers of agencies to contact for more information; (2) availability of qualified personnel to address civic, religious, social, and occupational organizations; and (3) distribution of news material to the media.
Emergency information will be made available to transient populations through the distribution of safety information brochures to commercial establishments in the 10-mile EPZ. A supply of these brochures is maintained at motels within the 10-mile EPZ.
Lake warning signs are posted at boat ramps, or access roads to boat ramps, at Harris and Jordan Lakes. These signs describe the activities which would be taken to initiate an evacuation of the lake and actions which should be taken in response to the evacuation. The posting of these signs is verified semiannually.
During an actual emergency, provisions will be established through the Joint Information Center to make available and distribute information to the news media. Provisions for a number of telephones which members of the public, who hear rumors, can call for factual information will also be implemented in the JIC when activated.
The public education program is further described in Section 5.2.6.
PLP-201 Rev. 26 Page 83 of 131
5.2.6 Public Education State of North Carolina The North Carolina Department of Crime Control and Public Safety has overall responsibility for maintaining a continuing disaster preparedness public education program. Such a program, prepared by the state of North Carolina, with the cooperation of the local governments and CPaL, is intended to ensure the members of the public are:
- a. Aware of the potential threat of a radiological emergency;
- b. Able to recognize a radiological emergency notification; and ce Knowledgeable of the proper immediate actions (return to home, close windows and tune to an Emergency Alert System station) to be taken.
A program of this type includes education on protective actions to be taken shelter is prescribed and the general procedures to follow if if an evacuation is required. Zt also includes general educational information on radiation and how to learn more about emergency preparedness.
Additional information about public education and information can be found in Section 5.2.5 5.3 Drills and Exercises 5.3.1 Drills Emergency Plan Implementation Procedure PEP-406 prescribes policies and procedures for conducting the following drills:
Communication Drills Communication from the Plant to the State and local government warning points within the plume exposure pathway Emergency Planning Zone shall be tested monthly.
Communications from the Main Control Room, Technical Support Center, and the Emergency Operations Facility to the NRC Headquarters Operations Center shall be tested monthly.
- 3. Communications between the nuclear facility, state, and local emergency operations centers, and environmental monitoring teams shall be tested annually.
Communications between the Main Control Room, the Technical Support. Center and the Emergency Operations Facility shall be tested annually.
Fire Drills Fire drills shall be conducted in accordance with Section 13.2 of the FSAR.
Co Medical Emer enc Drills A medical emezgency drill involving a simulated contaminated individual with, provision for participation by the local support services agencies (that is, ambulance, and off-site medical treatment facility) shall be conducted annually.
The off-site portions of the medical drill may be conducted once per calendar year.
PLP-201 Rev. 26 Page 84 of 131
5.3.1 Drills (continued)
- d. Environmental Monitorin Drills Plant environs and radiological monitoring drills (on site and off site) shall be conducted annually. These drills shall include collection and analysis of all sample media (such as water, vegetation, soil, and air), and provisions for communications and record keeping.
- e. Radiolo ical Control Drills Radiological Control drills shall be conducted semiannually which involve response to, and analysis of, simulated elevated airborne and liquid samples and direct radiation measurements in the environment.
Analysis of in-plant liquid samples with actual elevated radiation levels including use of the post-accident sampling system shall be included in Radiological Control drills annually.
Critiques and evaluation of drills will be conducted by a qualified individual. The degree of participation by outside agencies in conducting these drills may vary and their action may actually be simulated.
5.3.2 Exercises An exercise is an event that tests the integrated capability of major response organizations. Exercises shall test the adequacy of timing and content. of implementing procedures and methods, test emergency equipment and communications networks, and ensure that emergency organization personnel are familiar with their duties. Procedures for the conduct of exercises are described in the Plant Emergency Procedure PEP-406. An emergency exercise involving on-site participation will be conducted at least once each calendar year.
Partial participation exercises involving off-site agencies will be conducted at least once every second calendar year (IE Information Notice 85-55).
Partial participation means appropriate off-site authorities shall actively take part in the exercise sufficient to test direction and control functions to include protective action decision making related to emergency action levels and communication capabilities among affected state and local authorities and CP&L.
Every sixth year the exercise will include the full participation of the State. These full participation exercises will include appropriate off-site local and state authorities and CP&L personnel physically and actively taking part in testing the integrated capability to adequately assess and respond to an accident at the plant. "Full participation" includes testing the major observable portions of the on-site and off-site emergency plans and mobilization of state, local, and CP&L personnel and other resources in sufficient numbers to verify the capability to respond to the accident scenario.
Exercises involving off-site agencies will simulate an emergency that results in an off-site radiological release.
The annual exercises should be conducted during different seasons of the year and some exercises will be unannounced.
The scenario will be varied from year to year such that all elements of the plans and emergency organizations are tested within a 6-year period. One exercise shall start between 6 p.m. and 4 a.m. once every 6 years.
PLP-201 Rev. 26 Page 85 of 131
5.3.2 Exercises (continued)
Advance knowledge of the scenarios will be kept to a minimum to allow "fzee-play" decision making and to ensure a realistic participation by those involved.
Each annual exercise plan should include the following:
The basic objective(s) of the exercise.
The date(s), time period, place(s), and participating organizations.
The simulated events.
A time schedule of real and simulated initiating events.
A narrative summary describing the conduct of the exercise to include such things as simulated casualties, off-site fire department assistance, rescue of personnel, use of protective clothing, deployment of radiological monitoring teams, and public information activities.
Arrangements for qualified Evaluators and Controllers.
Critique and Evaluation Reports.
Prior to the exercise, an exercise plan will be distributed to the exercise controllers and evaluators that will include a list of performance objectives, the scenario, and a description of the expected responses.
Qualified observers from CP&L, federal, state, or local governments will observe and critique each annual exercise in which the state and counties participate. A critique will be scheduled at the conclusion of each exercise to evaluate the ability of all participating organizations to respond. The ~
critique will be held as soon as possible after the exercise. A formal written evaluation of the exercise will be prepared by the Emergency Planning Coordinator following the critique.
The Plant Emergency Planning Coordinator or his designee will determine those critique items that require corrective actions. Plant administrative controls will be utilized to ensure that corrective actions aze implemented.'.4 Maintenance and Inventor of Emer enc E ui ment and Su lies 5.4.1 Emer enc E ui ment and Su lies A resource list of emergency equipment and supplies to be inventoried for the TSC, OSC, and EOF is referenced in the implementation procedures. This listing provides information on location and availability of emergency equipment and supplies.
An inventory of all emergency equipment and supplies is held on a quarterly basis and after use in an emergency or drill. During this inventory, radiation monitoring equipment is to be checked to verify that required calibration and location are in accordance with the inventory lists.
Respiratory protection equipment, maintained for emergency purposes, is to be inspected and inventoried monthly.
5.4.2 Medical E ui ment and Su lies At least twice each year and after use in an emergency or drill, emergency medical equipment and supplies located in the First Aid Room and the contents of first aid kits located throughout the plant are to be inventoried, inspected, replaced, and replenished and/or resterilized as necessary. First Aid Team personnel inspect and inventory emergency medical supplies required to support a medical emergency at the plant, and plant personnel use the checklist in the applicable procedures to inspect other emergency items located in the First Aid Room.
PLP-201 Rev. 26 Page 86 of 131
5.4.3 Meteorolo ical Instrumentation Calibration of and channel checks on meteorological instrumentation are performed in accordance with Technical Specifications.
6.0 RECOVERY 6.1 General The overall goals of the recovery effort are to assess the in-plant consequences of the emergency and perform cleanup and repair operations.
effort includes marshalling of the Corporate resources and interfacing withThis outside agencies. All recovery actions will be preplanned in order to minimize radiation exposure or other hazards to recovery personnel.
The recovery organization may begin to develop plans for recovery of the facility while the emergency is still in progress. However, these will not be permitted to interfere with or detract from the efforts efforts to control the emergency situation. During the emergency phases of the incident, the recovery organization resources will be available to assist and provide support for the Site Emergency Coordinator.
6.2 Recover Or anization The recovery organization consists of the Recovery Manager, managers of support functions who are responsible to the Recovery Manager, and supporting personnel. This organization may be modified during the recovery process to better respond to the conditions at the plant. A block diagram of the recovery organization is presented in Figure 6.2-1. Personnel designated to assume responsibility of each of the activities shown in the block diagram are indicated in PEP-500.
The state will be the lead organization for off-site recovery operations. The state's recovery organization will be in accordance with the North Carolina Emergency Response Plan.
6.3 Assi nment of Res onsibilities 6.3.1 Recover Mana er The recovery organization, under the direction of the Recovery Manager, have the following responsibilities:
will
- a. Assess and determine the overall damage.
- b. Develop a recovery plan.
- c. Identify resources needed to complete the recovery.
Obtain any services and equipment necessary to complete the needed repair.
Conduct post-accident evaluations of the causes and consequences of the incident.
Obtain all necessary licenses, or amendments to licenses, required for repair of the Unit and disposal of radioactive waste products.
Coordinate with local and state agencies to keep them informed of on-site activities on a timely basis and provide support for any off-site protective actions required during the recovery operations.
PLP-201 Rev. 26 Page 87 of,131
6.3.1 Recover Mana er (continued)
Coordinate NRC activities at the site in an effort to avoid duplication and minimize impact on the plant staff.
Control personnel exposure during re-entry and recovery operations.
6.3.2 General Mana er Harris Plant The General Manager - Harris Plant is responsible for implementation of in-plant recovery activities with the objective of maintaining safe shutdown conditions and controlling sources of radioactivity in the plant. The General Manager Harris Plant will report to the Recovery Manager during recovery operations.
Responsibilities of the General Manager Harris Plant and his staff include the following:
a ~ Direct operations of the plant site including approval and implementation of engineering modifications, special tests and experiments, and maintenance operations to zecover from the incident.
- b. Identify and repair any damage to the facility.
co Provide continuing security protection as required for the plant site.
- d. Provide on-site health physics support including on-site sampling, dose assessment, dose management, and radiation protection programs.
- e. Provide information and recommendations to the Recovery Manager concerning future operations that could affect the plant or the environment.
- f. Provide assessment of the cause of the emergency.
Provide technical support to the Recovery Manager in systems analysis, core analysis, operating and maintenance procedure revisions, licensing information development and coordination, plant systems design data development, continued assessment of plant systems interaction, and continued determination of the safety status of the plant.
Assist the Recovery Manager in establishing a list of plant equipment/system modifications required for plant safe cold shutdown, plant cleanup, and plant restart.
Coordinate and supervise the modification and repair work performed by outside contractors.
6.3.3 Mana er - Harris En ineerin Su ort Section The Manager Harris Engineering Support Section is responsible for engineering and design support to meet requirements of the recovery operation.
Responsibilities include:
Provide engineering support to the Recovery Manager in assessing the cause of the emergency and the extent of equipment and systems damage.
PLP-201 Rev. 26 Page 88 of 131
6.3.3 Mana er - Harris En ineerin Su ort Section (continued)
Develop an engineering support plan compatible with the overall plant recovery plan. This plan will include allocation of engineering personnel resources.
Coordinate and supervise the engineering work performed by the Harris Engineering Support Section and other engineering consultants.
- d. Coordinate the timely transmittal of engineering modification design documents (specifications and drawings) to appropriate organizations.
- e. Provide technical interface as authorized by the Recovery Manager to utility groups, consultants, technical investigation groups, and regulatory agencies.
Assess the impact of the incident on continued operation of other CP&L nuclear plants, and submit results of this assessment to the Recovery Manager for review and subsequent submittal to CP&L Management.
6.3.4 Mana er Outa e & Schedulin The Manager Outage and Scheduling coordinates the construction activities to meet the requirements of the recovery operation.
Responsibilities include:
Develop an outage plan, including the allocation of contractor personnel, to support the timely completion of identified plant modifications and repairs required during the recovery process.
Coordinate the timely transfer of installed equipment and/or systems (modifications) to Plant Operations in accordance with the established recovery procedures.
6.3.5 Administrative and Lo istics Mana er The Administrative and Logistics Manager provides administrative, logistic, communications, and personnel support for the recovery operation.
Responsibilities include:
a Provide assistance to the Recovery Manager in the planning, scheduling, and expediting of recovery operations.
- b. Coordinate the use of communications personnel from other departments to install, maintain, and operate on-site communications facilities needed to carry out the recovery plan.
Provide purchasing personnel responsible for locating, ordering, and receiving equipment and materials needed to carry out the recovery plan.
- d. Maintain an inventory of materials, supplies, and equipment that may be needed and locate potential suppliers.
Provide processing of expense accounts, distribution of checks from payroll, and administration of other financial aspects of the recovery organization.
PLP-201 Rev. 26 Page 89 of 131
6.3.5 Administrative and Lo istics Mana er (continued)
Provide logistics arrangements for support personnel called in to assist in the recovery operations, including communications hardware, transportation, room and board.
Establish and maintain a cost control/accounting system for the recovery operation.
Determine additional contracts, facilities, and services required by the recovery organization and provide these facilities and servi ces.
Serve as a liaison between the Recovery Manager and the Legal Department.
Provide appropriate Corporate and Contractor insurance personnel to process claims for financial losses resulting from emergency activities.
Establish and maintain a document control system for the recovery operation.
Provide administrative services for the recovery organization such as clerical, typing, and duplication.
Provide support for the screening, orientation, and badging of support personnel.
- n. Process invoices from supporting utilities and contractors .whose personnel were obtained through mutual aid agreements.
6.3.6 Radiolo ical Control Mana er The Radiological Control Manager is responsible for providing radiation protection and radioactive waste disposal plans consistent with the recovery operation.
Responsibilities include:
Assist the Recovery Manager by providing As Low As Reasonably Achievable (ALARA) review of engineering modifications and tasks proposed by the recovery organization, including necessary documentation of those reviews.
- b. Coordinate with the Manager Harris Engineering Support Section in the design of special packaging required for the transport of radioactive waste resulting from the incident and recovery operation.
Assist in assessment of off-site radiological consequences of the incident. Coordinate and communicate with the State the results of radiological assessments.
Develop methods for sampling, treatment, and/or disposal of radioactive wastes resulting from the emergency and recovery operation.
- e. Provide consultation, support, review, and inspection of special waste treatment facilities.
PLP-201 Rev. 26 Page 90 of 131
6.3.6 Radiolo ical Control Mana er (continued)
Provide dose calculations to the Recovery Manager for total population exposure based on data from available sources and/or mathematical modeling.
6.4 Recover Plan Activation Once the Site Emergency Coordinator and the Emergency Response Manager have determined that recovery efforts can begin, the Emergency Response Manager will activate the recovery organization and become the Recovery Manager.
Implementation of Recovery Operations would occur as follows:
- 1. Transition from Emergency to Recovery
- 2. Activation of Recovery Organization The decision to de-escalate or terminate the emergency condition and begin recovery operations may be based on the following considerations:
Stability of the reactor shutdown condition, that is, successful progress toward a cold shutdown condition.
- b. Integrity of the Reactor Containment Building.
c Operability of radioactive waste systems and decontamination facilities.
- d. The availability and operability of a heat sink.
- e. The integrity of power supplies and electrical equipment.
The operability and integrity of instrumentation including radiation monitoring equipment.
- g. Availability of trained personnel and support services.
Radiation levels in plant areas are stable or decreasing with time.
Releases of radioactive materials to the environment from the plant are under control or have ceased.
Any fire, flooding, or similar emergency conditions are controlled or have ceased.
- k. Reduced or removed security threat.
Decisions to relax protective actions for the public will be made in accordance with the North Carolina Radiological Emergency Plan. The Recovery Manager will provide information to the appropriate state agencies to facilitate the decision.
Notification of on-site and off-site organizations that the Recovery Organization is to be activated will be initiated by the Emergency Response Manager and will follow plant emergency notification procedures.
Notification will follow the plant emergency procedures summarized in Section 4.2 of the Plan, except that the notification message will state that the Recovery Plan has been initiated and will list the new positions of the Recovery Organization. The notification time limits will not be applied.
PLP-201 Rev. 26 Page 91 of 131
6.5 Recover Plannin Recovery from an emergency situation is guided by the following principles:
The protection of the public health and safety is the foremost consideration in formulating recovery plans.
- b. Public officials are kept informed of recovery plans so that they can properly carry out their responsibilities to the public.
Periodic briefings of media representatives are held to inform the public of recovery plans and progress made.
Periodic status reports are given to company employees at other locations and to government and industry representatives.
The radiation doses to employees and other radiation workers are kept As Low As Reasonably Achievable (ALUM).
Necessary adjustments in the size and makeup of the Recovery Manager's staff are made as deemed necessary by the Recovery Manager.
6.6 Reentr Plannin The plans and procedures for area reentry will be developed at the time and will consider existing as well as potential conditions inside affected areas.
Prior to reentry, the Recovery Manager and staff shall:
a ~ Review all available radiation survey data and determine plant areas potentially affected by radiation exposure and contamination.
- b. Review the radiation exposure records of personnel participating in the recovery operation and determine the need for additional personnel.
Review the adequacy of the radiation sampling and survey instrumentation to be used by the team (type, ranges, number, calibration, and so forth).
Review protective clothing, dosimetry, and respiratory protection needs.
Ensure appropriate communications are available.
Ensure all team members are briefed concerning areas to be entered, anticipated radiation levels, access control procedures, and methods and procedures that will be employed during the entry.
The initial entry into the affected area should encompass the following actions:
Conduct a comprehensive radiation survey of the plant facilities and define all radiological problem areas.
Isolate and post with appropriate warning signs all radiation and contamination areas.
Identify potential hazards associated with the recovery operation.
PLP-201 Rev. 26 Page 92 of 131
6.7 Total Po ulation Ex osure Estimates The Radiological Control Manager will periodically update the estimate of total population exposure. The estimate will be determined from data collected in cooperation with the state.
The North Carolina Division of Radiation Protection (DRP), Department of Environment, Health and Natural Resources will be the lead state agency in the collection and analysis of radiation monitoring reports and of environmental aiz, foliage, food, and water samples. The DRP will be assisted by qualified personnel from HNP.
Total population exposure will be periodically determined through a variety of procedures including:
- a. Examination of prepositioned TLDs.
- b. Bioassay
- c. Estimates based on release rates and meteorology.
Estimates based on environmental monitoring of food, water, and ambient dose rates.
6.8 Recover Termination and Re ortin Re uirements Responsibility for providing a closeout verbal summary and written summary to off-site authorities after the accident is the responsibility of the General Manager Harris Plant. These summaries should be simple and in sufficient detail only to define that the accident situation is ended.
Reports to the NRC are in accordance with 10CFR50.72, 10CFR20, Subpart M, and the HNP Technical Specifications, Section 6.9.
PLP-201 Rev. 26 Page 93 of 131
Figure 6.2-1 Recovery Organization Recovery Manager General Manager- Company Harris Plant Spokesperson Radiation Control Manager Nuclear Regulatory
.Commission Manager-Outage 8 Scheduling State and County Agencies Manager - Harris Engineering Support Section Other Federal Agencies Administrative 8 Logistics Manager LEGEND OPERATION INFORMATlON J
PLP-201 Rev. 26 Page 94 of 131
7.0 REFERENCES
- 1. HNP Plant Operating Manual.
- 2. CP&L Radiation Control and Protection Manual.
- 3. CP&L Corporate Emergency Plan.
Final Safety Analysis Report (FSAR), Carolina Power & Light Company, Shearon Harris Nuclear Power Plant.
- 5. EPA 400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, " U.S. Environmental Protection Agency.
- 6. EPPOS No. 1, "Emergency Preparedness Position (EPPOS) on Acceptable Deviations from Appendix 1 of NUREG-0654 Based Upon the Staff's Regulatory Analysis of NUMARC/NESP-007, 'Methodology for Development of Emergency Action Levels'.
- 7. NUREG-0654/FEMA-REP-1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, October 1980, Revision l.
- 8. NUREG-0654/FEMA-REP-1, Revision 1, Supplement 1, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, Criteria for Utility Offsite Planning and Preparednes's, August 1988
- 9. NUREG-0737, Clarification of TMI Action Plan Requirements, dated October 1980.
- 10. NUREG-0737, Supplement 1, Requirements for Emergency Response Capability, December 1982.
- 11. NUREG-0696, Functional Criteria for Emergency Response Facilities, Final Report, February 1981.
- 12. Title 10, Code of Federal Regulations.
- a. Part 20, Standards for Protection Against Radiation
- b. Part 50, Licensing of Production and Utilization Facilities C>> Part 50, Appendix E, Emergency Plans for Production and Utilization Facilities
- 13. Federal Re ister, Vol. 43, No. 242, December 15, 1978'PS Food and Drug Administration, Accidental Radioactive Contamination of Human Food and Animal Feeds.
- 14. IE Information Notice No. 83-28, Criteria for Protective Action Recommendations for General Emergencies, May 4, 1983.
PLP-201 Rev. 26 Page 95 of 131
ANNEX A This Annex contains a list of written agreements between CPRL and other organizations that may be required to provide support to the Harris Nuclear Plant in the event of an on-site radiological emergency. Agreements with The original letters and reconfirmations of the a reements are on file in the HNP EP office.
Date of Original Contract/
A reement Or anization A reement Latest Reconfirmation Dates
- 1. Fuquay-Varina Rural Fire Department, Inc. - Contract 06-16-88 Expires 12-31 No Reconfirmation Necessary
- 2. Holly Springs Rural Fire Dept., Inc. - Contract 10-16-86 Expires 10-16 No Reconfirmation Necessary
- 3. Apex Rescue Squad, Inc. - Contract 01-29-87 Expires 02-01 No Reconfirmation Necessary
- 4. Rex Hospital 11-16-82 08-10-95
- 5. Wake Medical Center 05-20-87 08-10-95
- 6. Western Wake Medical Center 04-22-92 08-03-95
- 7. Douglas I. Hammer, M.D. 10-17-94 08-02-95
- 8. Stephen E. Johnson, M.D. 10-31-94 08-11-95
- 9. Donald E. Vaughn, M.D. 10-28-94 08-02-95
- 10. Nuclear Power Plant Emergency Response 07-01-82 Does not require updating.
Voluntary Assistance Agreement Signature Page
- 11. Institute of Nuclear Power Operations 10-14-85 Does not require updating.
- 12. National Weather Service 11-04-85 08-02-95 I certify that the agreements contained herein are current through annual reconfirmation, where required, or through personal verification of current applicability where reconfirmation Emerg anni oordinator/repre entative is not required.
ANNEX B TECHNICAL BASIS OF EMERGENCY DOSE PROJECTION PROGRAM
~neck roundWhen a potential or actual unanticipated releaae of radioactive material occurs which causes or may potentially cause a radiation monitor (as shown on Table 2 of this annex) to go into high alarm, a dose projection is performed. Initially, prior to activation of the Emergency Operations Facility, the Control Room staff is responsible for perfozming dose projections. Once the Emergency Operations Facility is activated, the radiological control staff assumes responsibility for dose projections. These dose projections are used to classify emergencies, formulate follow-up protective action recommendations to the State and Counties, and to characterize the overall health risk to the public of any releases. The methodology for dose projections is based upon the referenced documents at the end of this discussion. The methods, assumptions and equations used to estimate projected doses are presented herein.
The exposure to the public during an airborne release (early phase) is via direct exposure to an overhead plume or immersion in a radioactive plume, direct exposure from deposited radioactive materials, and the committed dose to internal organs from inhalation of radioactive materials. These doses are expressed in terms of Total Effective Dose Equivalent, which is the sum of external exposure doses from the plume and deposited materials and the internal dose commitment from intake of radioactive materials, and Committed Dose Equivalents to the critical organ (Thyroid), which is the radiation dose due to radionuclides in the thyroid over a 50-year period following intake.
The fundamental equation used to estimate projected dose is:
D = X/Q DCF [Reference 1]
Where:
D = Dose in Rem [TEDE or CDE]
X/Q = Atmospheric Dispersion Coefficient in Sec./M'
= Radioactive Source Term in Curies DCF = Dose Conversion Factor in (Rem - M~) / (Ci Sec.)
As shown, three components are required to project the dose to the public.
The first factor, X/Q, is derived from data obtained from the plant's meteorological tower. The parameters of wind speed, wind direction, and differential temperature are measured by instruments on the tower and aze used in the Gaussian diffusion model [References 2 and 3] to derive the X/Q factor.
The second part of the equation, Q, or source term, is determined from plant effluent monitor reading(s), from analysis of a sample of effluent gas or water, from selection of a default accident category, or from a manual method of analysis.
The last part of the equation, DCF, or dose conversion factor, is taken from the EPA "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" [Reference 4].
Implicit in the dose equation are input variables such as estimated duration of release and distances from the release point to points of interest.
PLP-201 Rev. 26 Page 97 of 131
ANNEX B TECHNICAL BASIS OF EMERGENCY DOSE PROJECTION PROGRAM II. Source Term A. Back round Since 1962, source term mixes for nuclear power plants have been derived from TID-14844 [Reference 5]. This report established what, was believed to be a bounding case for release of radionuclides in a severe core damage accident.
The release consisted of 100% of the core inventory of noble gases, 50% of the core inventory of iodines, and 1% of the core inventory of particulates.
Since that time the use of probabilistic risk assessments in examining accident consequences has been developed and has culminated in the NRC report NUREG-1465, "Accident Source Terms for Light Water Nuclear Power Plants"
[Reference 6]. In this document, new source terms were proposed that utilized the risk assessments of five typical PWRs and five BWRs to develop a mean in-containment isotopic release fraction for various core damage events.
In any risk assessment study, a large number of accident sequences and their probabilities of occurrence are analyzed. A separate isotopic release fraction is developed for each accident sequence. The major isotopic release fractions are those fractions of core inventory that are released either through failure of the fuel cladding, melting of the core within the reactor vessel or release of melted core materials through a breach of the reactor vessel. These fractions are values that when multiplied by the core inventory in curies of the particular isotopes, give curie amounts of isotopes immediately available for release from the containment. The effects of cleanup and engineered safety features are taken into account to the extent consistent with the failures that led to the particular accident sequence. To make the results manageable, the accident sequences and the accident isotopic releases are grouped. NUREG-1465 then uses the accident sequence probabilities as a means to weigh the release fractions for that sequence category. The weighted release fractions are added up to determine a "mean" in-containment release fraction.
B. Source Term Cate pries The traditional source term categories used in the industry were based on TID-14844 and utilized the major accidents analyzed in the FSAR, that is, LOCA, and so forth. The source term based on TID-14844 was a default mix of isotopes that was acted upon by the available engineering safety features and natural phenomena associated with each analyzed accident.
The new source terms are based upon the core melt sequences developed by the methodologies used in risk assessment studies. These sequences look at four categories of core damage: 1) fuel clad failure, 2) in-vessel melting,
- 3) rx-vessel release through a breach of the vessel by melted fuel, and a late in-vessel melting category. These categories have an associated release duration based upon the length of time that the core is uncovered. As a result, it is possible to construct a source term mix matrix that is dependent on two parameters, whether or not the fuel is uncovered, and the length of time that the fuel is uncovered.
PLP-201 Rev. 26 Page 98 of 131
ANNEX B TECHNICAL BASIS OF EMERGENCY DOSE PROJECTION PROGRAM B. Source Term Cate pries (continued)
In order to select the proper mix, the release pathway and estimated time duration of coze uncovery will be determined. The response to the release pathway questions and core uncovery time should result in the selection of one of eight possible accident source term mixes as shown in Table B.l-1. The late in-vessel melt release fractions in the risk assessment studies are approximately one order of magnitude below the early in-vessel values, so no separate category of source terms were developed for that case.
As a special case, aged spent fuel involved in shipments and long-term storage have a single isotopic inventory for the gap which consists of long-lived isotopes'his inventory will be used as a single case for determination of a source term for dose assessment purposes.
The maximum expected inventory of a waste gas decay tank will be used as a single mix category (with no decay).
C. Radioisoto e Inventories and Assum tions The radionuclides included in the mixes were taken from RTM-92. Additional radioisotopes were taken from the plant's core damage assessment procedure not already included. Isotopes that had no in-containment release fractions if given in the reference documents were removed from the list.
The core inventories for Harris were developed using the ORIGEN code assuming an average end of life burnup of 39 GWD/MTU'. The fuel used in the analysis was Siemens 17x17 HTP with 4.95% enriched U~".
The aged spent fuel assembly source term was developed by taking the values for Kr" and I"'rom the ORIGEN code run, decaying the values for 5 years, and then taking release fractions as stated in Regulatory Guide 1.25 (30%)
[Reference 8] .
The Waste Gas Decay Tank for the Harris Plant mix is taken from Tables 11.3.2-7 and 12.2.1-21 of the FSAR.
D. Develo ment of Source Terms Based on Default Accident Cate pries In the absence of better information, such as an effluent monitor reading or an effluent sample, a dose projection can be performed simply by specifying the accident category as a default. The selection of a default accident category defines the mix, the total curies, and the release pathway(s). The total number of curies from the default mix foz each isotope is used to provide an upper bound for Q, and hence, an upper bound for the dose to the public.
ED Develo ment of Source Terms Based on Effluent Monitor Readin s Radiation monitors in effluent streams or other release pathways are used to define a release activity based on the sensitivity of the monitor to the particular radionuclide mix. The effect of radioactive decay in changing the mix of isotopes is taken into account up to a maximum decay from time of reactor shutdown of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />. Two types of monitors are used, effluent monitors and other radiation monitors.
'igawatt days per metric ton of uranium.
PLP-201 Rev. 26 Page 99 of 131
ANNEX B TECHNICAL BASIS OF EMERGENCY DOSE PROJECTION PROGRAM E. Develo ment of Source Terms Based on Effluent Monitor Readin s (continued)
Effluent monitors are calibrated to a reference Xe-133 standard and are sensitive to both betas and gammas. The sensitivity of the monitor varies with the energy of the betas and gammas detected, and this sensitivity curve is used to develop an accident specific sensitivity for the monitor which is converted to a Xe-133 equivalent. The radionuclide mix for each accident category is thus converted into a multiplication factor for the calibrated detector sensitivity. This modified sensitivity is then multiplied by the process flow to provide a curies/second source term for each radionuclide present. The estimated duration of release, based on an assessment of the accident duration, is multiplied by the curies/second to derive a total curie release for each isotope.
Radiation monitors that are not a part of effluent streams utilize a detector sensitive only to gammas. These monitors also have a sensitivity that varies with the energy of the gamma. The radionuclide mixes aze modeled with the detector geometry to develop an accident specific sensitivity. The radionuclide mix for each accident category is thus converted into a multiplication factor for the calibrated detector sensitivity. This modified sensitivity is then multiplied by the process flow to provide a curies/second source term for each radionuclide present. The estimated duration of release, based on an assessment of the accident duration, is multiplied by the curies/second to derive a total curie release for each isotope.
F. Develo ment of Source Terms Based on Effluent Sam les Effluent samples, when analyzed, will provide a decay corrected activity from time of reactor shutdown expressed in terms of pCi/cc for each isotope. These values are then multiplied by the process flow to provide a cuzies/second source term for each radionuclide present. The estimated duration of release, based on an assessment of the accident duration, is multiplied, by the curies/second to derive a total curie release for each isotope.
G. Develo ment of Source Terms b Manual Method There may be occasions where "what-if" calculations may be necessary in the decision-making process. The dose projection procedure will allow the input of a direct curie value for each isotope in the source term.
III. Atmos heric Dis ersion The model used to predict the reduction in concentration of radionuclides as a function of meteorological conditions and distance is the Gaussian Plume Model using the Pasquill Dispersion Model [References 2 and 3].
Two meteorological parameters are needed to compute the atmospheric dispersion factor X/Q. They are wind speed and the stability class as determined the differential air temperature as a function of height above ground level. by These two parameters can be obtained in one of four ways:
The plant computer (ERFIS) polls the meteorological tower data acquisition system every 15 minutes and reports the most recently obtained data.
A personal computer can dial the meteozological tower data acquisition system and obtain current data.
PLP-201 Rev. 26 Page 100 of 131
ANNEX B TECHNICAL BASIS OF EMERGENCY DOSE PROJECTION PROGRAM III. Atmos heric Dis ersion (continued)
- 3. The Weather Center can be contacted to provide information which can be used to derive the required parameters.
4, The National Weather Service can be contacted to provide information which can be used to derive the required parameters.
The differential temperature as a function of height above ground level at the meteorological tower is used to determine the Pasquill stability class as A through G, where A is the most unstable atmosphere and G is the most stable.
The X/Q value is calculated as a function of wind speed, stability class, and distance from the plant.
IV. Dose Conversion Factors Dose Conversion Factors for each isotope in the source term aze taken entirely from the EPA "Manual of Protective Action Guides and Protective Actions from Nuclear Incidents" (Reference 4). The EPA assumptions on particle size, deposition velocity, the presence of daughter products of decay, and exposure duration incorporated into the Dose Conversion Factors are also incorporated into the dose assessment model by reference.
To determine the Total Effective Dose Equivalent, the DCFs from Table 5-1 in Reference 4 are multiplied by the individual souzce term curies for each isotope, times the X/Q. The result is a TEDE for each isotope. The TEDE doses of all the isotopes aze summed to provide a Total Effective Dose Equivalent in the dose projection results.
To determine the Committed Dose Equivalent to the thyroid, the DCFs from Table 5-2 in Reference 4 are multiplied by the individual source term curies for each iodine isotope, times the X/Q. The result is a 50 year committed dose equivalent to the thyroid for each isotope. The CDE doses are summed to provide a total thyroid CDE in the dose projection results.
V. Assum tions and Limitations A. Source Terms Core buznup was assumed to be an average end-of-life composed of the latest fuel manufacture.
The radionuclide mix was taken as a representative sample of noble gas, halogen, and particulate isotopes with short-, medium-, and long-term decay constants, of high quantity production, with some isotopes having high DCFs.
The selection of isotopes is consistent with Reference 7.
The noble gas source term will be reported as xenon-133 equivalent.
The radioiodine source term will be reported as iodine-131 equivalent.
Source terms are decayed from reactor shutdown (where values are assumed at equilibrium) to the time of release into the environment. The decay affects the mix of isotopes. Radioactive decay during plume passage will not be calculated.
PLP-201 Rev. 26 Page 101 of 131
ANNEX B TECHNICAL BASIS OF EMERGENCY DOSE PROJECTION PROGRAM V. Assum tions and Limitations (continued)
B. Atmos heric Dis ersion The X/Q values are based on data obtained from one meteorological tower site near the plant, and the information is assumed to be representative of the release point.
C. Dose Conversion Factors Deposition velocity is assumed to be 1 cm/sec. for radioiodines and .1 cm/sec.
for all other isotopes subject to deposition.
The duration of exposure to deposition will be four days.
The adult thyroid dose conversion factors are from Table 5-2 of Reference 4, and assume a breathing rate of 1.2 x 10'm'er hour.
The external dose to the thyroid is not added to the thyroid Committed Dose Equivalent to create a "Total Organ Dose Equivalent."
References:
Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, U.S. Nuclear Regulatory Commission, Washington, D.C., October 1975.
- 2. Regulatory Guide 1.145, "Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants, " U.S. Nuclear Regulatory Commission, Washington, D. C., August 1979.
- 3. "Workbook of Atmospheric Dispersion Estimates, " D. Bruce Turner, U.S.
Environmental Protection Agency, Washingtong D C ~ ~ p 1970.
EPA-400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," U.S. Environmental Protection Agency, Washington, D.C., May 1992.
Technical Information Document (TID)-14844, Calculation of Distance Factors for Power and Test Reactor Sites," J. J. DiNunno et al g UPS.
Atomic Energy Commission, Washington, D.C., 1962.
NUREG-1465, "Accident Source Terms for Light Water Nuclear Power Plants, " Draft Report for Comment, U.S. Nuclear Regulatory Commission, Washington, D.C., June 1992.
RTM-92, "Response Technical Manual," Vol. 1, Rev. 2, U.S. Nuclear Regulatory Commission, Washington, D.C., October 1992.
Regulatory Guide 1.25, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility foz Boiling and Pressurized Water Reactors, " U. S. Nuclear Regulatory Commission, Washington, D. C.,
March 1972.
PLP-201 Rev. 26 Page 102 of 131
Table B.l-l Source Term Categories Normal RCS Accidents that do not result in core uncovery.
No Fuel Failure Filtration and/or containment sprays are considered to With Cleanup be effective.
Gap Release Any accident sequence that results in core uncovery With Cleanup < 30 minutes, or mechanical fuel damage has occurred.
Filtration, partitioning and/or containment sprays are considered to be effective.
Gap Release Any accident sequence that results in core uncovery No Cleanup < 30 minutes or mechanical fuel damage has occurred.
Filtration, partitioning, and/or containment sprays are considered to be NOT effective.
Early 1V Any accident sequence that results in core uncovery With Cleanup from .5 to 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Filtration, partitioning, and/or containment sprays are considered to be effective.
Early IV Any accident sequence that results in core uncovery No Cleanup from .5 to 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Filtration, partitioning, and/or containment sprays are considered to be NOT effective.
Ex-Vessel Any accident sequence that, results in core uncovery With Cleanup > 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Filtration, partitioning, and/or containment sprays are considered to be effective.
Ex-Vessel Any accident sequence that results in core uncovery No Cleanup > 1.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Filtration, partitioning, and/or containment sprays are considered to be NOT effective.
Spent Fuel An Accident involving the damage of a freshly unloaded With Cleanup spent fuel assembly. Filtration is considered to be effective. For spent fuel assembly accidents with no filtration, use "Gap Release No Cleanup."
Waste Gas An Accident involving damage to a single waste gas Decay Tank decay tank with a maximum allowable isotopic inventory and no effective filtration.
PLP-201 Rev. 26 Page 103 of 131
Table B.1-2 Radiation Monitors Used as Radioactive Release Indicators INSTRUMENT TAG RM-11 ERFIS DESCRIPTION NO. ADDRESS POINT ID Main Steam Line A 1MS-3591-SB 5AX164 RMS3591A Main Steam Line B 1MS-3592-SB 5AX165 RMS3592A Main Steam Line C 1MS-3593-SB SAX166 RMS3593A Plant Vent Stack 1 WRGM 21AV-3509-1-SA 1EX817 RAV3509H Effluent Channel WPB Vent Stack 5 WRGM 1WV-3546-1 4EX837 RWV3546H Effluent Channel WPB Vent Stack 5A WRGM 1WV-3547-1 4EX847 RWV3547H Effluent Channel Containment High Ran e 1CR-3589-SA 2AX162 RCR3589A Containment High Ran e 1CR-3590-SB 2AX163 RCR3590A PLP-201 Rev. 26 Page 104 of 131
ANNEX C GLOSSARY OF TERMS Accident Assessment Accident assessment consists of a variety of actions taken to determine the nature, effects, and severity of an accident and includes evaluation of reactor operator status reports, damage assessment reports, meteorological observations, seismic observations, fire reports, radiological dose projections, in-plant radiological monitoring, and environmental monitoring.
Activate To formally put on active duty with the necessary personnel and equipment to carry out the function required, such as to activate the Technical Support Center (TSC) or the Emergency Operations Facility (EOF).
Alertin /Warnin , Public The process of signaling the public, as with sirens, to turn on their TVs or radios and listen for information or instructions broadcast by state or local government authorities on the Emergency Alert System (EAS).
Assessment Actions - Those actions taken during or after an accident to obtain and process information which is necessary to make decisions to implement specific emergency measures.
Command and Control Exercising the authority to coordinate and utilize an organization's resources to respond to an emergency condition.
Committed Dose E uivalent (CDE) - The Dose Equivalent to organs or tissues of reference that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.
Corrective Action Those emergency measures taken to lessen or terminate an emergency situation at or near the source of the problem, to prevent an uncontrolled release of radioactive material, or to reduce the magnitude of a release. Corrective action includes, equipment repair or shutdown, installation of emergency structures, fire fighting, repair, and damage control.
Lee, Harnett, and/or Wake County(ies).
Dama e Assessment Estimates and descriptions of the nature and extent of damages resulting from an emergency or disaster; of actions that can be taken to prevent or mitigate further damage; and of assistance required in response and recovery efforts based on actual observations by qualified engineers and inspectors.
Dama e Control The process of preventing further damage to occur and preventing the increase in severity of the accident.
Decontamination - The reduction or removal of contaminated radioactive materia from a structure, area, material, object, or person. Decontamination may be accomplished by (1) treating the surface so as to remove or decrease the contamination, (2) letting the material stand so that the radioactivity is decreased as a result of natural decay, and (3) covering the contamination.
DEM - An abbreviation standing for North Carolina Division of Emergency Management. DEM is the State agency responsible for preparing and maintaining a State Radiological Emergency Response Plan and for assembling and dispatching a State Emergency Response Team (SERT) to the scene of an emergency.
PLP-201 Rev. 26 Page 105 of 131
ANNEX C GLOSSARY OF TERMS Dose Pro'ection - The calculated estimate of' radiation dose to individuals at a given ocation (normally off site), determined from the source term/quantity of radioactive material (Q) released, and the appropriate meteorological dispersion parameters (X/Q).
Dose Rate - The amount of ionizing (or nuclear) radiation to which an aauaaua ual would be exposed per unit of time. Rs to a person, it it would is usually expressed as rem per hour or inapply to dose rate submultiples of this unit, such as millirem per hour. The dose rate is commonly used to indicate the level of radioactivity in a contaminated area.
Dosimeter An instrument such as a thermoluminescent dosimeter (TLD),
sae-reading pocket dosimeter (SRPD), or electronic dosimeter (ED) for measuring, registering, or evaluating total accumulated dose or exposure to ionizing radiation.
Drill A supervised instruction period aimed at testing, developing, and maxntaining skills in a particular operation.
Earl Phase The period at the beginning of a nuclear incident when immediate ecxszons or effective use of protective actions are required and must be based primarily on predictions of radiological conditions in the environment.
This phase may last from hours to days. For the purposes of dose projections it is assumed to last four days.
Emer enc Action Levels (EALs) Plant conditions used to determine the exes ence o an emergency an to classify its severity. The conditions include specific instrument readings, alarms, and observations that in combination indicate that an emergency initiating event has occurred and therefore an appropriate class of emergency should be declared. EALs cover a broad range of events such as radioactive releases to the environment, loss of all on-site and off-site power, security threats, fire, strikes of operating employees.
Emer enc Alert S stem (EAS) - A network of broadcast stations and xnterconnectxng acr sties which have been authorized by the Federal Communications Commission to operate in a controlled manner during a war, state of public peril or disaster, or other national emergency as provided by the Emergency Alert System Plan. In the event of a nuclear reactor accident, instructions/notifications to the public on conditions or protective actions would 'be broadcast by state or local government authorities on the EAS.
Emer enc 0 eratin Procedures (EOPs) - EOPs are step-by-step procedures for erect actions a en y xcense reactor operators to mitigate and/or correct an off normal plant condition through the control of plant systems.
Emer enc 0 erations Center (EOC) A facility designed and equipped for e ective coor z,na son an con rol of emergency operations carried out within an organization's jurisdiction. The site from which civil government officials (Municipal, County, State, and Federal) exercise direction and control in a civil defense emergency.
Emer enc O erations Facilit (EOF) The EOF is a CPaL facility near the p an t a zs prove e or t e management of overall CP&L emergency response in the event of a nuclear accident at the plant. Upon activation of the EOF, it assumes for the Technical Support Center (TSC) the function of providing support to the state on off-site radiological and environmental assessments, coordination with Federal, State, and Local Government officials on recommendations for public protective actions and direction of recovery operations.
PLP-201 Rev. 26 Page 106 of 131
ANNEX C GLOSSARY OF TERMS Emer enc Plannin Zones (EpZ) - A generic area defined about a nuclear plant to ace, state emergency p anna.ng off site. The plume exposure EPZ is described as an area with approximately a 10-mile radius and the ingestion exposure EPZ is described as an area with approximately a 50-mile radius, both of which are centered at the plant site.
Emer enc Pze aredness A state of readiness that pzovides reasonable assurance t at a equate protective measures can and will be taken upon implementation of the emergency plan in the event of a radiological emergency.
Evacuation - The urgent removal of people from an area to avoid or reduce
~xg i~eave, short-term exposure usually from the plume or from deposited activity.
Evacuation, Exclusion Area The evacuation of nonessential personnel from the Exc uszon Area.
Evacuation, Local The evacuation of personnel from a particular area, such as a room or uz ding.
Evacuation, Site The evacuation of nonessential personnel from the plant sate.
Exercise - An event that tests the integrated capability of a major portion of
'ttte asac elements existing within emergency preparedness plans and organizations.
Exclusion Area An Exclusion Area is an area specified for the purpose'f reac or sx e evaluation in accordance with 10CFR100. It is an area of such size that an individual located at any point on its boundary for two hours immediately following onset of the postulated release would not receive a total radiation dose to the whole body in excess of 25 rem or a total zadiation dose of 300 rem to the thyroid from iodine exposure. The exclusion area around HNP is CP&L-owned property with a radius of approximately 7000 feet.
Fission Product Barrier The fuel cladding, reactor coolant system boundary, or t e containment oundary.
Fission Product Barrier Status a Breached The fission product barrier is incapable of sufficiently retaanang radioactive materials to protect the public.
~Jeo ~ard Conditions exist that are likely to result in fission product.
barrier breach, but the barrier is intact at the present time.
Intact The fission product barrier retains the ability to protect the pgugac from a harmful release of radioactive materials.
Health Ph sics Network (HPN) Line In the event of a site emergency, the NRC HPN one wz e activate y t e NRC Operations center in Bethesda, Maryland.
This phone is part of a network that includes the NRC Regional Office and the NRC Operations Headquarters in Bethesda, Maryland. This system is dedicated to the transmittal of radiological information by plant personnel to NRC Operations Center and the Regional office. HPN phones are located in the TSC and EOF.
PLP"201 Rev. 26 Page 107 of 131
ANNEX C GLOSSARY OF TERMS In estion Ex osure Pathwa The potential pathway of radioactive materials to tsuche puas milk xc t roug consumption of radiologically contaminated water and foods or fresh vegetables. Around a nuclear power plant this is usually described in connection with the 50-mile radius Emergency Planning Zone (50-mile EPZ).
Intermediate Phase The period beginning after the source and releases have een roug t un er control and reliable environmental measurements are available for use as a basis for decisions on additional protective actions.
Joint Information Center - An Emergency Facility activated by CP&L and staffed y CP&L, State, an County Public Information personnel. This facility serves as the single point of contact for the media and public to obtain information about an emergency.
Late Phase - The period beginning when recovery action designed to reduce rraaxa ron levels in the environment to acceptahle levels for unrestricted use are commenced and ending when all recovery actions have been completed. This period may extend from months to years (also referred to as the recovery phase).
Main Control Room The operations center of a nuclear power plant from which t e p an can e monitored and controlled.
Monitorin , Environmental The use of radiological instruments or sample co ecting evzces to measure and assess background radiation levels and/or the extent and magnitude of radiological contamination in the environment around the plant. This may be done in various stages such as preoperational, operational, emergency, and post operational.
Monitorin , Personnel The determination of the -degree of radioactive contanu.nation on xn xviduals, using standard survey meters, and/or the determination of dosage received by means of dosimetry devices.
Notification, Public - Public notification means to communicate instructions on e na ure o an incident that prompted the public alerting/warning and on protective or precautionary actions that should be taken by the recipients of the alert. A state and local government process for providing information promptly to the public over radio and TV at the time of activating the alerting (warning) signal (sirens). Initial notifications of the public might include instructions to stay inside, close windows, and doors, and listen to radio and TV for further instructions. Commercial broadcast messages are the primary means for advising the general public of the conditions of any nuclear accident. (See Emergency Alert System.)
NRC Emer enc Notification S stem (ENS) The NRC Emergency Notification System ot one xs a e xcate te ep one system that connects the plant with NRC headquarters in Bethesda, Maryland. It is directly used for reporting emergency conditions to NRC personnel.
Off-Site The area outside of an approximate 2500-foot radius from the plant
~center ane, exclusive of the area cleared for plant construction.
on-site The area inside of an approximate 2500-foot radius from the plant centerTine, inclusive of the area cleared for plant construction, and including all permanent and temporary buildings, and the parking lots.
PLP-201 Rev. 26 Page 108 of 131
ANNEX C GLOSSARY OF TERMS O erational Su ort Center (OSC) - An emergency response facility at the Plant to w zc support personne report and stand by foz deployment in an emergency situation.
Plume Ex osure Pathwa The potential pathway of radioactive materials to the pu zc t roug a) w ole body external exposure from the plume and from deposited materials, and (b) inhalation of radioactive materials.
Po ulation-at-Risk Those persons for whom protective actions are being or wou e ta en. In the 10-mile EPZ the population-at-risk consists of resident population, transient population, special facility population, and industrial population.
Potassium Iodide (Symbol KI) A chemical compound that readily enters the yrox g an w en ingested.
exposure to radioactive iodine, If taken it in a sufficient quantity prior to can prevent the thyroid from absorbing any of the potentially harmful radioactive iodine-131.
Procedure, Plant Emer enc (PEP) - Plant emergency procedures implement the HNP Emergency P an an are pu bshed in Volume 2, Part 5 of the Plant Operations Manual. PEPs define the specific, step-by-step actions to be followed by the emergency organization in the process of recognizing and assessing an emergency condition, and mitigating the condition through the use of corrective and protective actions. PEPs do not include those actions taken by licensed control operators, to directly control plant systems (see Emergency Instructions).
Pro'ected Dose - An estimate of the potential radiation dose which affected popu a son groups could receive.
Protected Area An area of the plant site encompassed by physical barriers to w xc access xs controlled.
Protection Factor (PF) The relation between the amount of radiation which wou e receive y a completely unprotected person compared to the amount which would be received by a protected person such as a person in a shielded area. PF = Unshielded dose rate . shielded dose rate.
Protective Action Sometimes referred to as protective measure. An activity con ucte xn response to an incident or potential incident to avoid or reduce radiation dose to members of the public.
Protective Action Guide (PAG) The projected dose to reference man or other e one zn ave ua rom an accidental release of radioactive material at which a specific protective action to reduce or avoid that dose is warranted.
Reco~ver - The process of reducing radiation exposure rates and concentrations C
~o racCxoactive material in the environment to levels acceptable foz unconditional occupancy or use.
Release Escape of radioactive materials into the uncontrolled environment.
Restricted Area -Any area, access to which is controlled by Carolina Power &
Lzg t Company or purposes of protection of individuals from exposure to radiation and radioactive materials.
PLP-201 Rev. 26 Page 109 of 131
ANNEX C GLOSSARY OF TERMS Safet Anal sis Re ort, Final (FSAR) - The FSAR is a comprehensive report that a utx sty xs require to su rru.t to the NRC as a prerequisite and as part of the application for an operating license for a nuclear power plant. The multivolume report contains detailed information on the plant's design and operation, with emphasis on safety-related matters.
Safet -related As used in this plan and in Plant Emergency Procedures when escrow xng areas, equipment, systems or components, safety-related means:
- 1. Forming a part of the Reactor Coolant System pressure boundary, or
- 2. Used to mitigate the consequences of an abnormal condition, or
- 3. Necessary to achieve or maintain safe shutdown of the plant.
SERT State Emergency Response Team (North Carolina). (See also DEM)
Shelter A habitable structure or space used to protect its occupants from xacaaataon exposure. The radiation protection factor (PP) of the shelter will vary as a function of the density of structural materials located between its occupants and the source of radiation.
~ahieldin: Any material or harrier that attenuates Istops or reduces the xntenszty of) radiation.
Source Term Radioisotope inventory of the reactor coze, or amount of State - The State of North Carolina.
Technical Su ort Center (TSC) A center outside of the Main Control Room in w xc xn ormatxon xs supp xe on the status of the plant to those individuals who are knowledgeable or responsible for engineering and management support of reactor op'ezations in the event of an emergency, and to those persons who are responsible for management of the on-site emergency response.
Total Effective Dose E uivalent (TEDE) The sum of external and internal zonxzxng ra ration exposure.
Unrestricted Area Any area to which access is not controlled by the licensee or protec xng xndividuals from exposure to radiation and radioactive materials, and any area used for residential quarters.
PLP-201 Rev. 26 Page 110 of 131
ANNEX D NUREG-0654 REV. 1 Cross-Reference NUREG-0654, Criterion Para ra h EP Section Number A. Assi nment of Res onsibilit A.l.a Identify response organizations Annex G A.l.b Concept of operations 2.0, 4.0 A.l.c Illustrate interrelationships Figures G-l, G-3 A.l.d Individual responsible for emergency response 2.3, 2.4.2 A.l.e Provision for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day response 2.2.2, 2.4 A.3 Agreements Annex A A.4 Individual responsible for resources 2.4.2, 2.4.10 B. On-site Emer enc Or anization B.1 Plant Emergency Organization 2.2.2 B.2 Assignment of Site Emergency Coordinator 2.2.2, 2.3 B.3 Line of succession SEC 2.2.2g 2.3, 2.4.2 B.4 Responsibilities SEC 2.3, 2.4.2 B.5 Emergency organization and assignments 2.2, 2.4, Table 2.2-1 Figures G-l, G-3 B.6 Interfaces Plant, State, Local, Corp, Figures 2.2-1, 2.4-1, Table 4.0-1, Annex G B.7 Corporate Emergency Organization 2.2.1 B.7.a Logistics support for emergency personnel 2.4.10.5 B.7.b Technical Support planning reentry, 2 2 lg 4 6~ 6 0
~ ~
recovery B.7.c Management to Government interface 2.4.2, 2.4.10.1 Annex G B.7.d Corporate news media coordination 2.4.8 B.8 Contractor and private assistant Annex G B.9 Local agency services Annexes A & G C. Emer enc Res onse Su ort and Resources C. l.a Titles authorized to request federal 2.3 assistance C. l.b Specific federal resources expected Section 4.1 of and delivery time Annex G, Table G.l-l C.l.c Airports, EOC, telephones, radios, 3 7 lp 3 7 2g 3 8~
~
available to assist federals 3.9.5, 4.4, Annex H c.2.b Licensee representative to principal government EOCs 2.4.9 C.3 Description of available radiological labs 3.9.7 C.4 Nuclear and other facilities or organizations 2.5, Annex G D. Emer enc Classification S stem D.1 Emergency classification system and EALS, 4.1, Figure 4.1-1, parameter values and equipment status Figure 4.1-2 D.2 Initiating conditions and FSAR accidents 4.1 PLP-201 Rev. 26 Page 111 of 131
ANNEX D NUREG-0654 REV. 1 Cross-Reference NUREG-0654'riterion Para ra h EP Section Number E. Notification Methods and Procedures E.1 Establish procedures for notification of 4.2 response organization and verification E.2 Establish procedures for alerting, 4.2, 4.3 notifying, and mobilizing response personnel E.3 Establish content of message 4.2 E.4 Make provision for follow-up message 4.2 E.6 Provide for alerting and notifying public 4.5.3, Annex H E.7 Provide narrative for public messages on 4.5.3 protective actions F. Emer enc Communications Establish organizational titles and 2.4.7, 3.8, 4.1 alternate means of primary and backup communications F.l.a Provide Telephone link and alternate for 2.4.7, 3 ~ 8, 4.1, 24-hour notification to state and local Annex G agencies F.l.b Provide for communications with 2.4.7, 3.8 contiguous state/local agencies F.l.c Provide for communications with Federal 2.4.7, 3.8 agencies F.1.d Communication between plant, EOF, 3.8 state and local EOCs and RM teams F.1.e Provide for alerting and activating 3.8.4, 4.2 emergency personnel F.1. f Communication between NRC, EOF and 3.8 environmental monitoring teams F.2 Communication link for fixed and mobile 3.8, 4.6.3.6.4 medical F.3 Conduct periodic testing of communication 5.3.1 system G. Public Education and Information G.1 Disseminate, annually, educational 5.2.5 information to public G.2 Disseminate, annually, educational 5.2.5 information for transient population G.3.a Designate contacts and space for media 3.6 G.3.b Provide space for media at the EOF 2.4.8, 3.6 G.4.a Designate a spokesperson 2.4.8 G.4.b Provide for timely exchange of 2.4.8 information between spokespersons G.4.c Provide for coordinated rumor control 2.2.1, 2.4 ~ 8, 3.6 G.S Provide annual training for media 5.2.5 PLP-201 Rev. 26 Page 112 of 131
ANNEX D NUREG-0654 REV. 1 Cross-Reference NUREG-0654, Criterion Para ra h EP Section Number H. Emer enc Facilities and E ui ment H. 1 Establish TSC and OSC 3.3, 3.4 H.2 Establish EOF 3.5 H.4 Provide for timely activation of 4.2, 4.3 facilities H.S.a Identify & establish on-site geophysical 3.9.2, 3.9.5 phenomena monitors H.5.b On-site radiological monitors: process, 3.9.3, 3.9.6 area, emergency.
H.5.c On-site Process monitors: reactor 3.9.1 coolant pressure, temperature, and so for th H.s.d On-site fire and combustion products 3.9.8 detectors H.6.a Provide access to off-site geophysical 3.9.2, 3.9.5 monitors H.6.b Access to off-site radiological 3.9.3, 3.9.6, 3.9.7 monitors and sampling H.6.c Access to off-site laboratories: fixed 3.9.7 or mobile H.7 Provide for radiological monitoring 3.5.3, 3.9.3, equipment off-site Table 3.1-1, 4.4.4 H.8 Provide meteorological instrumentation 3.9.5 and procedures H.9 Provide for OSC and special equipment 3.4, Table 3.1-1 in the OSC H. 10 Inspect emergency equipment and supplies 5.4.1 H. 11 Identify emergency kits by general Table 3.1-1 category H~ 12 Establish point near EOF for receipt of 2 4 10 ~ 3 ~ 3~ 3 ~ 5~ 3 9 7 environmental monitoring data I. Accident Assessment Identify plant system and effluent 4.1 parameters and instruments values Z.2 Post-accident sampling, radiation 3.9 monitors, and so forth Z.3.a Establish methods and techniques to 4.4, Annex B determine source terms Z.3.b Methods to determine magnitude of release 4.4, Annex B Z.4 Establish relationships for effluent 4.4, Annex B monitor readings I.5 Capability to acquire and evaluate 3.9.5 meteorological data Z.6 Procedure for assessment when 4.4.3, Annex B instruments off-scale I.7 Describe capability and resources for 2.4.10.3.4, Table 2.2-1, environmental monitoring Table 3.1-1, 4.4.4 Z.8 Assessment of environmental hazards from 2.4.10.3.4, 3.9.6, liquid or gas 3.9.7, 4.2, 4.4.4 Table 2.2-1 Z.9 Detect and measure radioiodine in the 3.9.6, 4.4.4 10-Mile EPZ.
Z.10 Procedure for dose or dose rate 4.4.3, Annex B projection PLP-201" Rev. 26 Page 113 of 131
ANNEX D NUREG-0654 REV. 1 Cross-Reference NUREG-0654, Criterion Para ra h EP Section Number J. Protective Res onse J.l.a Establish means and time to warn 4.6.1, 4.6.2 on-site employees and individuals in the exclusion area not on the ERO J.l.b Establish means and time to warn on-site 4.6.1, 4.6.2 visitors or visitors in the exclusion area J.1.c Establish means and time to warn contractor/construction personnel J.l.d Est. means and time to warn others 4.5.3, 4.6.1 J.2 Evacuation routes and transportation 4.6.2 for on-site people J.3 Provide radiation monitoring for people 4. 6.2 in J.2 J. 4 Provide decon capability at J.3 location 4.6.2, 4.6.3.1 J.S Account for personnel, ascertain missing 2.4.5.1, 2.4.5.2 individuals within 30 minutes of start 4.6.2 of emergency and account for on-site persons continuously thereafter.
J.6.a For individuals remaining or arriving Table 3.1-1, 4.6.3.3, respiratory 5.2.1 individuals remaining or arriving-protection'or Table 3.1-1, 4.6.3.3 protective clothing J.6.c For individuals remaining or arriving- Table 3.1-1, 4.6.3.3 radioprotective drugs J.7 Recommendations To Local Government 4.5 J.8 Evacuation time estimates 10-Mile EPZ 1.8, Table 1.8-2 J.10.a Maps-Evac. routes, areas, rad. sampling Annex H, 4.4.4, and monitoring points, reception and Annex G shelter areas J.10.b Map-Population by Sectors and local 1.8, Table 1.8-1 zones J.10.c Means for notifying transient and 4.5.3 resident population J. 10.m Bases for recommended protective 4.5.1, 4.5.2, actions; shelter, evac. time Table 4.5-1 Figure 4.5-1 K. Radiolo ical Ex osure Control K. l.a Exposure guidelines removal of injured 4.6.3.4 persons K. 1.b Exposure guidelines performing 4. 6.3. 4 corrective actions K. 1.c Exposure guidelines- performing 4.6.3.4 assessment actions K. 1.d Exposure guidelines providing first aid 4.6.3.4 K. l.e Exposure guidelines personnel 4.6.3.4 decontamination K.l. f Exposure guidelines providing ambulance 4.6.3.4 service K.l.g Exposure guidelines- medical treatment 4. 6.3.4 K.2 On-site radiation pro tection program- 2.4.6.7, 4.6.3.4 emergency PLP-201 Rev. 26 Page 114 of 131
ANNEX D NUREG-0654 REV. 1 Cross-Reference NUREG-0654, Criterion Para ra h EP Section Number K. Radiolo ical Ex osure Control (continued)
K.3.a Dosimetry 24-hour capability 4.6.3.2 K.3.b Emergency worker dosimeters and dose 2.4.6.7, 4.6.3.2 records K.5.a Decontamination guides action levels 4.6.3.6.3, Table 4.6-1 K.s.b Means for decontamination and waste 4.6.3.1, 4.6.3.6.3, disposal Table 4.6-1 K.6.a Contamination control access control 4.6.3.6.3, Table 4.6-1 K. 6.b Contamination control drinking water 4.6.3.8 and food K.6.c Criteria for return to normal use- 4.6.3.6.3 areas, items K.7 Decontamination relocated on-site 4.6.2, 4.6.3.1, personnel 4 '.3.6.3 L. Medical and Public Health Su ort L.l Local and backup hospital for evaluation 4.6.3.7.1, 5.1.1, of radiation exposure - adequately Annex A prepared L.2 On-site first aid capability 2.4.3.5, 4.6.3.6.2 L.4 Transportation - victims of radiation 4.6.3.6.4, Annex A accident M. Recover and Reentr Plannin and Post-Accident 0 erations M. 1 Plans and procedures - relaxation of 6.4, 6.5, 6.6 protective measures M.2 Recovery organization 6.2, Figure 6.2-1, 6.3 M.3 Means for alerting recovery personnel 4.2, 6.4 M.4 Method for periodically estimating 6.7 population dose N. Exercises and Drills N. 1.a Conduct annual exercise off-site 5.3.2 release N.1.b Verify capability to respond - Evaluate, Critique 5 '.2 N.2.a Conduct communication drills to test 5.3.1.a communications with: State & local in 10-mi: EPZ monthly; Federal & State in 50-mi. EPZ quarterly; plant, State &
local EOCs and field assessment teams annually.
N.2.b Conduct fire drills per plant tech specs 5.3.1.b N.2.c Medical emergency drill, contaminated 5.3.1.c individual & participation by local ambulance & off-site medical facility annually.
N.3.c Plans/Scenario content simulated events 5.3.2 N.3.d Plans/Scenario content time 5.3.2 N.3.e Plans/Scenario content - narrative 5.3.2 summary PLP-201 Rev. 26 Page 115 of 131
0 ANNEX D NUREG-0654 REV. 1 Cross-Reference NUREG-0654'riterion Para ra h EP Section Number N.3. f Plans/Scenario content - official 5.3.2 observers N.4 Provision for critiques 5.3.2 N.5 Provision for identifying areas of 5.3.2 improvement and assigning responsibility for corrective action
- 0. Radiolo ical Emer enc Res onse Trainin 0.1 Assure the training of individuals who 5.2 maybe called on to assist in an emergency O.l.a Provide training for off-site emergency 5.2.3 organizations 0.2 Training to include practical drills- 5.2.1 on-site organization 0.3 First aid team training to include 5.2.1 Multimedia 0.4.a Training of response organization 5.2.1 directors 0.4.b Training of accident assessment personnel 5.2.1 0.4.c Training of radiological monitoring and 5.2.1 analysis personnel 0.4.d Training of police, security, fire- 5.2.1 fighting personnel 0.4.e Training of repair and damage control 5.2.1 teams 0.4.f Training of first aid and rescue 5.2.1 personnel 0.4.g Training of local support service/CD 5.2.1, 5.2.3 0.4.h Training of medical support personnel 5.2.1, 5.2.3 0.4.i Training of headquarters support 5.2.2 personnel 0.4.j Training of emergency communicators 5.2.1 0.5 Provide initial and annual retraining 5.2.1 P. Res onsibilit for the Plannin Effort P.1 Provide training for emergency planners 5.2.4 P.2 Identify titles responsible for planning 1.3, 5.1.1 P.3 Designate Emergency Planning Coordinator 1.3, 5.1.1 P.4 Annually review and update plans and 5.1.2 agreements P.5 Distribute emergency plan; identify 5.1.2 revisions p.6 List other supporting plans 1.9 P.7 List and cross-reference procedures for 5.1.4, Annex E implementing the plan p.8 Provide Table of Contents and NUREG pgs.
5.1.5 i and ii, cross-reference Annex D P.9 Arrange independent review every 12 5.1.6 months P.10 Provide for quarterly updating of 5.1.3 telephone numbers PLP-201 Rev. 26 Page 116 of 131
ANNEX E LIST OF PLANT EMERGENCY PROCEDURES (PEP)
Implemented Plan Section 0.0 PLANT EMERGENCY PROCEDURES INTRODUCTION PEP - 001 Administration of Plant Emergency Procedures 1.2 1.0 EMERGENCY CLASSIFICATIONS AND CONTROL PROCEDURES PEP 100 Emergency Action Levels Users Guide 4.1 PEP 101 Emergency Classification and
- Initial Emergency Actions 4.1 PEP 102 Site Emergency Coordinator-Control Room 4.1, 2.4.2 PEP 103 Site Emergency Coordinator - TSC 4.1, 2.4.2 PEP 104 Protective Action Recommendations 45, 46, Annex G 2.0 EMERGENCY MANAGEMENT GUZDES PEP - 200 Emergency Response Organization Conduct 2.4 of Operations PEP - 201 Plant Operations Director 2.4.3 PEP - 202 Emergency Repair Director 2.4.4 PEP 204 Radiological Control Director 2.4.6 PEP - 206 Environmental Field Coordinator 2.4.10.3.3, 2.4.10.3.4 PEP 207 Chemistry Coordinator 2.4.6.5,
- 2.4.6.6, 4.4 PEP 208 Radiological Control Coordinator 2.4.6.7, 2.4.6.8 4.6.1, Annex A PEP 210 Security Director 2.4.5.3 PEP 211 Damage Control Coordinator 2.4,4.1, 2.4.4.2, 2.4.4.3 PEP 215 Admin Building Assembly Area Leader 2.4.5.4 PEP - 216 Dose Projection Team Leader 2.4.10.3.2
- 2.4.10.3.5 PEP 217 Emergency Communicators 2.4.7, 4.2 PEP 218 Technical Analysis Director 2.4.3.1 PEP 220 Emergency Response Manager 2.4.10.1 PEP 221 Technical Analysis Manager 2.4.10.4 PEP - 222 Administrative and Logistics Manager 2.4.10.5 PEP 223 Radiological Control Manager 2.4.10.3 PEP 250 Activation and Operation of the Joint Information Center 2.4.8 3.0 EMERGENCY ACTION PROCEDURES
- 3. 1 Communications Procedures PEP 301 Notifications of Non-CP&L Emergency Response Organizations 4.2, 3.8 PEP 302 Communications Activities 4.2, 3.8 PEP 304 Inadvertent Actuation of the Public Emergency Warning System 4.5.3 PLP-201 Rev. 26 Page 117 of 131
ANNEX E LZST OF PLANT EMERGENCY PROCEDURES (PEP)
Zmplemented Plan Section 3.3 Plant Monitoring Procedures PEP - 331 Emergency Plant Monitoring 3.4 Radiological Consequences PEP 343 Dose Projection 4.4.3, Annex B 3.5 Environmental Monitoring Procedures PEP - 351 Emergency Plant Environmental Monitoring 4.4.4 3.6 Estimates of Core Damage PEP 362 Core Damage Assessment 3.7 Radiation Control Procedures PEP 370 Radiological Controls for the Technical Support Center 4.6.3 PEP 371 Emergency Response in Radiological Areas 4.6.3 PEP - 374 Radiological Controls for the Emergency Operations Facility 4.6.3 3.8 Protective Action Procedures PEP 381 Evacuation 4.6.2 PEP - 382 Personnel Accountability 4.6.2 PEP 383 Administration of Potassium Zodide 4.6.3.3 PEP 384 Access Control 4.6.2 3.9 Aid to Affected Personnel PEP 391 First Aid and Medical Care 2.4.3.5 4.6.3.6 PEP 394 Search and Rescue 4.6.2 4.0 SUPPLEMENTAL PROCEDURES PEP 401 Record Keeping and Documentation 2 ~ 4I 5 1 2I 5.1.6 PEP 402 Maintaining Readiness of Emergency 3.0, 5.4
- Facilities PEP 403 Performance of Training 5.2 PEP 405 Preparation of Activity Logs 2.4 PEP 406 Performance of Exercises and Drills 5.3 PEP - 407 Maintenance of the HNP 2.0, 5.0 Emergency Response Organization 5.0 RECOVERY PROCEDURES PEP 500 Recovery 6.0 6.8 Emergency Phone List (EPL-001) 5. 1. 3, Annex G
PLP-201 Rev. 26 Page 118 of 131
ANNEX F Deleted by Revision 19 The warning message form used to notify the state and Counties is provided in Annex F of the North Carolina Emergency Response Plan and is included as a form in PEP-301, "Notification of Non-CP&L Emergency Response Organizations."
Rev. 26 Page 119 of 131
ANNEX G INTERFACING INFORMATION FROM SUPPORTING EMERGENCY PLANS 1.0 General The material in this Annex is included as general information on how supporting emergency plans interface with the HNP Emergency Plan. The information is presented in a similar format as the basic Plan. Emergency organization interfaces, based on levels of activation, are depicted in Figures G-1 and G-3. A summary of organizations expected to support emergency response is contained in Table G.l-l.
2.0 HNP Emer enc 0 erations Facilit When activated, the Emergency Response Manager's organization assembles in the Emergency Operations Facility (EOF). The EOF functions under the Emergency Response Manager, who is responsible for the overall company activities relating to the emergency and for coordinating those activities with participating governmental agencies. The EOF organization and responsibilities are described in Section 2.4.10 of the Emergency Plan.
3.0 Coordination with Partici atin State and Local Government A encies 3.1 State of North Carolina Governor's Office The Governor has the authority to direct and control the State Emergency Management Program, During a declared State of Disaster, he has the authority to utilize all available state resources reasonably necessary to cope with emergencies. His representatives coordinate as necessary with Carolina Power & Light Company (CP&L) and with local government officials.
3.2 North Carolina De artment of Crime Control and Public Safet The Department of Crime Control and Public Safety functions as the State of North Carolina Emergency Planning Coordinator. In that capacity, the Department has overall management responsibility for North Carolina's radiological emergency response planning, development, updating, and coordination with CP&L. The Department coordinates emergency response activities for the State of North Carolina and other government emergency response agencies.
The Department, through its State Highway Patrol, provides the notification point for the State.
initial 24-hour emergency 3.3 North Carolina Division of Emer enc Mana ement The Division of Emergency Management (DEM) is the responsible organization within the N.C. Department of Crime Control and Public Safety to prepare and maintain a State Radiological Emergency Response Plan for HNP in coordination with the Department of Environment, Health and Natural Resources and other interested agencies. The DEM is the lead response agency within State government and coordinates the activities in the State Emergency Respons Team (SERT) Headquarters and the State Emergency Operations Center (SEOC) in Raleigh. Personnel within the SERT Headquarters and the SEOC will confer with CP&L to determine appropriate emergency response activities which should be taken to protect the health and safety of the public.
PLP-201 Rev. 26 Page 120 of 131
ANNEX G INTERFACING INFORMATION FROM SUPPORTING EMERGENCY PLANS 3.4 North Carolina De artment of Environment, Health and Natural Resources, Dxvxsxon o Ra matron Protection The Division of Radiation Protection (DRP), within the Department will be the lead agency in the collection and analysis of radiation monitoring reports and of environmental air, foliage, food, and water samples. The DRP will be assisted by qualified personnel from HNP.
3.5 Chatham Count De artment of Emer enc 0 erations The Chatham County Department of Emergency Operations acts as the Chatham County Emergency Management Agency and operates the County Warning Point and the Communications Center.
The Chatham County Department of Emergency Operations has the following responsibilities:
- Develop and maintain Chatham County's Plan to Support the Harris Nuclear Power Plant.
Coordinate emergency response matters between the State, County, CP&L, and local government agencies.
- Operate the county warning point (Communications Center) on a 24-hour basis. The Communications Center is manned continuously by a Public Safety Dispatcher.
- Coordinate the protective response operations required by the Chatham County Plan to Support the Harris Nuclear Power Plant during an emergency.
3.6 Harnett Count Emer enc Mana ement A enc The Harnett County Emergency Management Agency has the following responsibilities:
- Develop and maintain the Harnett County's Plan to Support the Harris Nuclear Power Plant.
Coordinate emergency response matters between the State, County, CP&L, and local government agencies.
- Coordinate the protective response operations required by the Harnett County Plan to Support the Harris Nuclear Power Plant during an emergency.
3.7 Harnett Count Sheriff's De artment The Sheriff's Department operates the county warning point on a 24-hour basis.
The county warning point is the Sheriff's Department communications center which is manned continuously by a Public Safety Dispatcher.
PLP-201 Rev. 26 Page 121 of 131
ANNEX G INTERFACING INFORMATION FROM SUPPORTING EMERGENCY PLANS 3.8 Sanford-Lee Count Emer enc Mana ement A enc The Sanford-Lee County Emergency Management Agency has the following responsibilities:
- Develop and maintain the Sanford-Lee County's Radiological Emergency Response Plan to Support the Harris Nuclear Power Plant.
Coordinate emergency response matters between the State, County, CP&L, and local governmental agencies.
- Coordinate the protective response operations required by the Sanford-Lee County Plan to Support the Harris Nuclear Power Plant during an emergency.
3.9 Lee Count Sheriff's De artment The Sheriff's Department operates the county warning point on a 24-hour basis.
The county warning point is the Lee County communications center which is manned continuously by a Public Safety Dispatcher.
3.10 Wake Count Emer enc Mana ement A enc The Wake County Emergency Management Agency has been assigned the following responsibilities:
- Develop and maintain Wake County's Plan to Support the Harris Nuclear Power Plant.
Coordinate emergency response matters between the State, County, CP&L, and local government agencies.
Coordinate the protective response operations required by the Wake County Plan to Support the Harris Nuclear Power Plant during an emergency.
3.11 Ralei h Communications Center The Raleigh City Communications Center provides emergency telephone notification service and serves Wake County and all municipalities within the county as the 24-hour warning point. The warning point is manned continuously by a Public Safety Dispatcher.
4.0 Coordination With Federal A encies and Other States 4.1 De artment of Ener , Savannah River 0 erations Office The role of the Department of Energy is described in the Federal Radiological Emergency Response Plan published in the Federal Re ister, Volume 50, No. 217, November 8, 1985.
4.2 Federal Emer enc Mana ement A enc (FEMA)
The role of the Federal Emergency Management Agency (FEMA) is described in the Federal Radiological Emergency Response Plan.
PLP-201 Rev. 26 Page 122 of 131
ANNEX G INTERFACING INFORMATION FROM SUPPORTING EMERGENCY PLANS 4.3 Nuclear Re ulator Commission (NRC)
The Nuclear Regulatory Commission provides at least one resident inspector at HNP. Upon notification by Carolina Power & Light Company, NRC provides additional technical advice, technical assistance, and personnel per NUREG-0728, "Report to Congress, NRC Incident Response Plan, " and NUREG-0845, "Agency Procedures for the NRC Incident Response Plan" and supplements. The NRC Operations Center will be notified of radiation incidents in accordance with 10CFR 50.72 using the Emergency Notification System (ENS) phone.
4.4 Weather Service The National Weather Service at the Raleigh-Durham Airport, Raleigh, North Carolina, will provide meteorological information during emergency situations, if required. Data available will include existing and forecasted surface wind directions, wind speed with azimuth variability, and ambient surface air temperature.
5.0 Contracted Services A number of active contracts are maintained in order to ensure continuing access to qualified personnel when and resources.
if they are needed to supplement CP&L These contracts provide the capability of obtaining, on an expedited basis, additional maintenance support personnel (such as mechanics, electricians, and Z&C Technicians), other technical personnel (such as HP and Chemistry Technicians), and engineering and consulting services. For example, contracts are maintained with Westinghouse, Daniel Construction, and Ebasco (the NSSS vendor, constructor, and architect-engineer respectively for HNP).
A contract is maintained with the Babcock & Wilcox Company for analysis of in-plant radioactive samples.
6.0 Institute of Nuclear Power O erations One of INPO's roles is to assist the affected utility in applying the resources of the nuclear industry to meet the needs of the emergency. When notified of an emergency situation, INPO will provide emergency response in accordance with the ZNPO Emergency Response Plan at the request of the utility. Utility emergency response planning includes notification to INPO, via the emergency telephone number, of events classified Alert or higher.
INPO is able to provide the following emergency support functions:
~ Identifying sources of emergency manpower
~ Dissemination of technical information concerning the incident to member utilities and participants
~ Analysis of operational aspects of the incident To support these functions, ZNPO maintains the following emergency support capabilities:
Dedicated emergency call number capable of reaching INPO staff and activating INPO support functions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day Designated INPO representative(s) who can be dispatched to the utility to coordinate ZNPO support activities and information flow PLP-201 Rev. 26 Page 123 of 131
ANNEX G INTERFACING INFORMATION FROM SUPPORTING EMERGENCY PLANS 6.0 Institute of Nuclear Power 0 erations (continued)
~ An Emergency Response Center available for operation 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day An ZNPO duty person will respond to the call, and the Emergency Response Center at INPO will be activated as necessary.
If requestedmembers qualified by the utility or when deemed appropriate, one or more suitably of the INPO staff will report to the Emergency Response Manager and assist in coordinating ZNPO's response to the emergency, as follows:
~ Staffing a position responsible to the appropriate utility manager as liaison foz all ZNPO matters
~ Working with INPO personnel in Atlanta to coordinate requests for assistance, ZNPO response, and related communications '
Assisting the utility as requested in the use of industry information systems (such as NETWORK) concerning accident status and related information of interest to other utilities
~ Ensuring that emergency information released by the ZNPO liaison is cleared through appropriate utility channels An INPO representative could be dispatched on approximately a four-hour notice. On-site activities, when undertaken, will be approved by the President of INPO and coordinated with the affected utility through the on-site ZNPO representative.
Carolina Power & Light Company is a signatory to the mutual assistance agreement developed by INPO for utilities in the nuclear industry.
7.0 Local Services Su ort is equipped and staffed to cope with many types of emergency situations.
HNP However, if a fire, medical, or other type of incident occurs that requires outside assistance, such assistance is available as shown on Table 4.0-1.
7.1 Medical Assistance Medical assistance is available through agreements with the following organizations as described in Section 4.6.3.7 of this plan:
Local area physicians Rex Hospital Wake Medical Center Western Wake Medical Center HNP agreements with the above listed agencies are on file at CP&L. Annex A lists the current status of each agreement.
7.2 Ambulance Service HNP maintains a contract for support services with Apex Rescue Squad, Inc. as described in Section 4.6.3.6.4 of this plan. Annex A lists the current status of this agreement.
PLP-201 Rev. 26 Page 124 of 131
ANNEX G INTERFACING INFORMATION FROM SUPPORTING EMERGENCY PLANS 7.3 Fire Assistance Agencies with fire protection resources in the vicinity of the Harris Nuclear Plant are as follows:
Fuquay-Varina Rural Fire Department, Inc.
Holly Springs Rural Fire Department, Inc.
Other Wake County Fire Departments The Holly Springs Rural Fire Department, Inc., is the primary fire protection response agency for HNP and will coordinate assistance activities, through a County-wide Mutual Aid Agreement of the other area Fire Departments. HNP agreements with Fuquay-Varina and Holly Springs Fire Departments are on file at CPaL. Annex A lists the current status of each agreement.
8.0 General Public Protective actions which should be taken by the general public will be provided by State and local government agencies. Carolina Power & Light Company will make recommendations to these government agencies as discussed in Section 4 of this Plan.
8.1 Evacuation
- In the event that evacuation of the plume exposure pathway EPZ is required, the evacuation routes shown in Annex H will be used by on-site personnel and the public.
The time required to evacuate personnel from the plume exposure pathway EPZ varies depending on whether a part of the EPZ is to be evacuated or all of it, or prevailing weather conditions, as provided in Table 1.8-2.
8.2 Shelter The decision to evacuate or remain (in shelter) should be based on an evaluation of many factors including the protection afforded by dwellings, public fallout shelters, and other structures that might provide protection from surface deposited radionuclides and from a gamma cloud source in the plume exposure pathway EPZ.
The locations of public shelters are depicted in Annex H.
PLP-201 Rev. 26 Page 125 of 131
Table G.1-1 Organizations Participating in Emergency Response Location for Approximate Agent for Bes pans@
- 1. HNP Site Emergency Coordinator Control Room 5 Minutes Superintendent - Shift Operations
- 2. Emergency Operations Emergency Response EOF, New Hill 60-75 Minutes Designated Individual Facility (EOF) Manager
- 3. Corporate Corporate Spokesperson JIC, Raleigh 1-2 Hours On call Corp.
Communications Communications
- 4. Nuclear Regulatory 1. Emergency Office (HQ) NRC Ops. Ctr Immediate HQ Duty Officer Commission 2. Base Team Mg (Reg.) Incident Response Immediate Regional Duty Officer Center
- 5. Nuclear Regulatory 1. Director-Site Team Ops EOF, New Hill 5-8 Hours Dir. of Site Team Ops Comm. (Site Team) 2. Interim Director EOF, New Hill 60-75 Minutes Resident Inspector
- 6. State Emergency SERT Coordinator Division Emer. 2 Hours Highway Patrol Response Team Management Hqtrs, Communications Center Raleigh
- 7. Chatham County EOC Country Board Chairman County Law 1 1/4- 2 Hours County Communications Enforcement Center Center, Pittsboro
- 8. Harnett County EOC County Board Chairman County Law 1 1/4- 2 Hours Sheriff's Department Enforcement Bldg. Lillington Lillington
- 9. Lee County EOC County Board Chairman Sanford Municipal 1-3 Hours Lee County Center, Sanford Communications Center, Sanford
- 10. Wake County EOC County Board Chairman County Courthouse, 1-2 Hours Raleigh Communications Raleigh Center
- 11. Fuquay-Varina Fire Chief HNP 20-30 Minutes Raleigh Communications Rural Fire Center Department
Table G.1-1 Organizations Participating in Emergency Response Location for Approximate Agent for Besponsa BespoasaZime
- 12. Apex Rescue Squad Captain HNP 30-45 Minutes Raleigh Communications Center
- 13. Holly Springs Rural Fire Chief HNP 30-45 Minutes Raleigh Communications Fire Department Center
- 14. Rex Hospital Emergency Room Rex Hospital, 30-45 Minutes Rex Emergency Room or Raleigh Raleigh Comm. Center
{WMC) or Raleigh Comm. Center
- 16. Western Wake Medical Emergency Room WWMC, Cary 20-30 Minutes WWMC Emergency Room Center (WWMC) or Raleigh Comm. Center
- 17. INPO Duty Officer Emergency Response 4-8 Hours Emergency Response Center, Atlanta Center, Atlanta
- 18. Westinghouse Emergency Response Command Center 8-16 Hours Regional Service Director Monroeville, PA Manager, Southern Service Region, Atlanta
- 19. Ebasco Emergency Response Team Emergency Response 8-16 Hours Emergency Response Manager Center, NY, NY Team Manager, New York, NY
- 20. American Nuclear Designated ANI Staff EOF, New Hill 24-48 Hours ANI Office, Farmingt CT Insurers (ANI)
- 21. Department of Energy Shift Lieutenant Emergency 4-17 Hours Emergency Operations Operations Center for Site Team Center, Aiken, Aiken, SC South Carolina
Figure G-1 Emergency Response Organization Interfaces, TSC and EOF Not Activated Site Emergency Coordinator (MCR)
North Carolina State On-Shift Local Fire, Division of Rescue and ERO Emergency Management Medical Support Chatham County Plant Emergency Management Westinghouse Management Agency Harnett County Corporate Emergency Management Ebasco Management Agency Sanford-Lee County NRC National Emergency Management Operations Weather Agency Center Service Wake County Emergency Management lNPO Agency Corporate Communications LEGEND Communication Request Assistance if Necessary PLP-201 Rev. 26 Page 128'of 131
Figure 6-2 Deleted by Revision 21 PLP-201 Rev. 26 Page 129 of 131
Figure G-3 Emer enc Or anization Interfaces TSC and EOF Activated Site Emergency Coordinator (MCR)
North Carolina State EOF Division of ERO Westinghouse Emergency Management (See Fig. 2.4-1)
Chatham County On-Site Emergency Management ERO Ebasco Agency (See Fig. 2.2-1)
Hamett County Local Fire, National Emergency Management Rescue and Weather Agency Medical Support Service Sanford-Lee County Department Corporate Emergency Management of Agency Management Energy Wake County American Emergency Management Nud ear Agency Insurers N.C. Department of NRC Quite Environmental Health Response and Natural Resources Team Corporate Communications INPO Joint Information Center LEGEND Communication Request Assistance if Necessary Rev. 26 Page 130 of 131
ANNEX H Operations Map Shearon Harris Nuclear Power Plant A folded copy of the "Operations Map Shearon Harris Nuclear Power Plant, " from Annex I of the "North Carolina Emergency Response Plan in Support of the Shearon Harris Nuclear Power Plant", is contained in the plastic sleeve following this page.
PLP-201 Rev. 26 Page 131 of 131
(
1