ML18141A505

Rev 10 to Emergency Plan Implementing Procedure EPIP-1.01, Emergency Manager Controlling Procedure. W/840217 Ltr

ML18141A505
Person / Time
Site:	Surry
Issue date:	02/02/1984
From:	Stewart W, Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
081, 81, EPIP-1.01-01, EPIP-1.01-1, NUDOCS 8402240032
Download: ML18141A505 (8)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY REVISIONS TO SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES Enclosed are recently revised pages to the Surry Power Station Emergency Plan Implementing Procedures. Please take the Iollowing actions in order to keep your manual updated with the most recent revisions.

EPIP-1. 01 EMERGENCY MANAGER CONTROLLING PROCEDURE Remove and Destroy Enter Page 1 of 8, Rev. 09 Pages 1 of 8 and and page 6 of 8, Rev. 6 of 8; Pages 6 of 39, 08; Pages 6 of 39, 7 of 39, 8 of 39 and 7 of 39, 8 of 39 and 9 of 39 of Attachment 1 9 of 39 of Attachment all Rev. 10.

1, all Rev. 08. Dated 02-02-84 8402240032 840202 PDR ADOCK 05000280 F PDR

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NO. 9?887230 REV:A e e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION 10 EPIP-l.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE (With 1 Attachment) 1 of 8 PURPOSE To initially assess a potential emergency condition and initiate corrective actions.

USER Shift Supervisor or Station Emergency Manager ENTRY CONDITIONS Any ~ of the following :

1. Another station procedure directs initiation of this procedure OR

2. A potential emergency condition is reported to the Shift Supervisor.

REVISION RECORD REV. 05 PAGE(S): 1 of 8, Att. 1 page 4, 22, and 23 of 39 DATE:03-10-83 REV. 06 PAGE(S): 1 of 8 and 4 of 8 DATE:03-11-83 REV. 07 PAGE(S): 1 Of 8, Att. 1 page 13 of 39 DATE:03-17-83 REV. 08 PAGE(S): 1, 5, 6 & 8; Att. 1, pgs. 2 through 13, 15, 17, 18, 20, and 23 through 38 DATE: 11-10-83 REV. 1 of 8 and 5 of 8 DATE:01-13-84 REV. 1, 6* Att. 1, pgs. 6, 7, 8 and 9 DATE: FEB O 2 1984 APPROVED DATE QC REVIEW

~J~,v,_ EB**2. 1984 OcHAl~~~N STATION NUCLEAR SAFETY

~'~ ANO OPERATING COMMITTEE

No, 978.8.7210 NUMBER 0

PROCEDURE TITLE

• REVISION

.. ******-. 10 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 6 of 8 STEP - - - ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

5. (CONTINUED) b) IF required, assign appropriate individual as interim Emergency Commun-icator c) IF required, direct senior H.P.

personnel on site to initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure

6. DETERMINE EPIPS:

a) Event classification - a) GO TO Step 6b of this in-NOTIFICATION OF UNUSUAL EVENT struction.

{

' 1) .QQ_1Q, EPIP-1.02,. Response to Notification of Unusual

-Event b) Event classification - ALERT b) GO TO Step 6c of this instruction.

1) GO TO EPIP-1.03, Response toAlert c) Event classification - SITE c) GO TO Step 6d of this AREA EMERGENCY instruction:-

1) GO TO EPIP-1.04, Response to Site Area Emergency d) Event classification -

GENERAL EMERGENCY

1) GO TO EPIP-1.05, Response to General Emergency

7. SECURE FROM EVENT:

a) Notify involved station personnel that emergency condition does not exist

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No. 97887220 e e NUMBER ATTACHMENT TITLE REVISION

,....,******. EPIP-1.01 10 ATTACHMENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 6 of 39 CONDITION/

APPLICABILITY INDICATION CLASSIFICATION

1. Safety Limit-RCS Limits of T.S. Fig. Notification of Temperature/Pressure 2 .1 EXCEEDED Unusual Event curve exceeded POWER & HSB

2. RCS overpressure 2735 psig RCS Notification of Pressure limit- Unusual Event EXCEEDED ALL CONDITIONS

3. Rx overpower 118% Rx thermal Notification of power limit - Unusual Event POWER EXCEEDED

4. RCS leak rate exceeds EP-2.00, Loss of Reactor Site Area 300 gpm Coolant - IMPLEMENTED Emergency ABOVE CSD CONDITION AND Pressurizer level can not be maintained with two (2)

Charging/SI Pumps in operation

5. RCS leak rate exceeds Unit in HSD or lower cond- Alert 50 gpm ition as a result of actions required IAW AP-16, ABOVE CSD CONDITION Excessive Primary Plant Leakage AND RCS inventory balance indi-cates leakage-GREATER THAN 50 gpm i',

No,97~l!7220 e

NUMBER ATTACHMENT TITLE REVISION i EPIP-1.01 10 ATTACHMENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 7 of 39 CONDITION/

APPLICABILITY INDICATION CLASSIFICATION

6. RCS leak rate requiring Unit in HSD or lower Notification of plant shutdown IAW as a result of any Unusual Event T.S. 3.1.C of the following:

POWER & HSB a) Unidentified RCS leakage-GREATER THAN.!_ gpm OR b) Identified leakage-GREATER THAN.!£. gpm OR c) Non-isolable fault of RCS pressure boundary

7. RCP locked rotor All the following Alert leading to fuel dam- exist:

age a) Flow in one or more POWER RC loops - LESS THAN 90%

AND b) RCP trip caused by Phase Overcurrent Relay - ACTUATION AND c) High Range Letdown Radiation Monitor indication increases to-GREATER THAN 5x10 5 cpm

No.978~7220 .e e NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 10 EMERGENCY ACTION LEVEL TABLE ATTACHMENT PAGE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 8 of 39 CONDITION/

APPLICABILITY INDICATION CLASSIFICATION

8. Gross Primary to EP-4.00, Steam Generator Site Area Secondary leakage with Tube Rupture - IMPLEMENTED Emergency loss of offsite power with SI in progress ABOVE CSD CONDITION AND Condenser Air Ejector Exhaust - DIVERT to Containment AND Loss of offsite power indi-cated by zero volts on volt-meters for 4160V Buses D, E

&F

9. Excessive Primary to Unit in HSD or lower Alert Secondary leakage with condition as a result of loss of offsite power actions required by T.S.

3.1.C.6 ABOVE CSD CONDITION AND Loss of offsite power indicated by zero volts on voltmeters for 4160V buses D, E & F.

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• No.978~7220 e NUMBER ATTACHMENT TITLE REVISION

/ EPIP-1.01 10 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB B) PAGE 1 REACTOR COOLANT SYSTEM EVENT 9 of 39 CONDITION/

APPLICABILITY INDICATION CLASSIFICATION

10. Gross Primary to EP-4.00, Steam Generator Alert Secondary leakage Tube Rupture - IMPLEMENTED with SI in progress ABOVE CSD CONDITION AND Condenser Air Ejector Exhaust - DIVERT to Containment

11. Primary to Secondary Unit in HSD or lower con- Notification of leakage-GREATER THAN dition as a result of Unusual Event 1 gpm actions required by T.S.

{ 3.1.C.6

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\ ABOVE CSD CONDITION

12. Loss of 2 of 3 fission Any two of a),b) or c) General Emer-product barriers with exist and the third gency potential loss of 3rd is imminent barrier a) Fuel clad integrity fail-ALL CONDITIONS ure as indicated by any of the following:

1) RCS specific activity -

GREATER THAN OR EQUAL TO 300.0 uCi/gram dose equivalent I-131.

2) 5 or more core exit thermocouples reading-GREATER THAN 1200°F OR b) Loss of RCS integrity as indicated by any of the following:

e GOV 02-54 VIRGINIA ELECTRIC AND PowER COMPANY R:ICHMOND, V:IRG:IN.IA 23261 February 17, 1984 Mr. James P. O'Reilly Serial No. 081 Regional Administrator NO/REB/vgv:EMl-17 U.S. Nuclear Regulatory Commission Docket Nos. 50--280 Region II 50-281 101 Marietta Street, Suite 2900 License Nos. DPR-32 Atlanta, Georgia 30303 DPR-37

Dear Mr. O'Reilly:

REVISIONS TO SURRY POWER STATION EMERGENCY PLAN DiPLEMENTING PROCEDURES Pursuant to 10CFR 50, Appendix E, paragraph 50.54 (q), rev1.s1.ons to the Surry Power Station Emergency Plan Implementing Procedures, numbers, and subjects as listed on enclosures are submitted.

Sincerely,

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w. L. Stewart Enclosures cc: Document Control Desk (2) w/o Enclosures cc: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Mr. D. J. Burke - (NRC - Surry)