ML032250417

Revision to Susquehanna Emergency Plan-Position Specific Procedure EP-PS-350, Public Information Manager

ML032250417
Person / Time
Site:	Susquehanna
Issue date:	07/31/2003
From:	Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML032250417 (4)

Text

Jul. 31, 2003 Page 1 of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-34470 USER INFORMATION:

Name:GERLACH*ROSE M EMPL#:28401 CA#:0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:

TO: GERLACH*ROSE M 07/31/2003 LOCATION: DOCUMENT CONTROL DESK -

FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)

'THE FOLLOWING CHANGES HAVE'OCCURRED'TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:

350 - 350 - PUBLIC INFORMATION MANAGER: EMERGENCY PLAN-POSITION SPECIFIC PROCEDURE REMOVE MANUAL TABLE OF CONTENTS DATE: 06126/2003

/D D MANUAL TABLE OF CONTENTS DATE: 07/30/2003 CATEGORY: PROCEDURES TYPE: EP ID: EP-PS-350 REPLACE: REV:14 REPLACE: REV:14 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

a.

Tab 13 EP-PS-350-13 ANTICIPATED QUESTION LIST The following questions are Intended to provide an overview of the event that precipitated entry Into the SSES EMERGENCY PLAN. They will be used by managers In the emergency response organization to better understand the situation and answer questions posed by offsfte agencies and regulators.

QUESTION #1: (TECHNICAL SUPPORT COORDINATOR/ENGINEERING SUPPORT SUPERVISOR)

What is the status of all three fission product boundaries? Indicate what data supports each determination.

a. Fuel cladding

b. Reactor coolant pressure boundary C. 'Primary containment QUESTION #2: (TECHNICAL SUPPORT COORDINATORIENGINEERING SUPPORT SUPERVISOR)

For intact barriers, what threats exist to their continued integrity? For degraded barriers, what.is the potential for further degradation? Indicate what data supports each determination.

a. Fuel cladding

b. Reactor coolant pressure boundary

c. Primary containment EP-AD-000-404, Revision 5, Page 1 of 3

Tab 13 EP-PS-350-13 ANTICIPATED QUESTION LIST QUESTION #3: (TECHNICAL SUPPORT COORDINATORIENGINEERING SUPPORT SUPERVISOR)

a. How is the core being cooled?

b. How do you know that the cooling system(s) in service are adequately removing heat from the core?

c. What backup cooling systems are available?

QUESTION #4: (TECHNICAL SUPPORT COORDINATORIENGINEERING SUPPORT SUPERVISOR)

a. How do you know that the core Is in a coolable configuration?

b. What is the current estimate of core damage?

c. What is the prognosis for further degradation?

QUESTION #5: (TECH SUPPORT COORDINATOR)

a. How do you correlate the in-plant radiological data with the In-plant system parameter data to support your understanding of the situation?

b. What is the status of off-site radiological releases?

EP-AD-000-404, Revision 5, Page 2 of 3

Tab 13 EP-PS-350-13 ANTICIPATED QUESTION UST

c. If releases are occurring:

1) What is the release path?

2) Is the release monitored?

3) Is the release filtered?

4) What Is the potential for increased release levels? When?

5) What is the potential for termination of the release? When-

c. If releases are not currently occurring:

1) What are the potentially releasable source terms?

2) What is the status of SBGTS?

QUESTION #6: (DOSE ASSESSMENT SUPERVISOR/RADIATION PROTECTION COORDINATOR)

a. If releases are occurring, what are the off-site release consequences?

b. What is the potential for the release to change and what would be the off-site consequences of the postulated release?

EP-AD-000-404, Revision 5, Page 3 of 3