ML18141A505

Rev 10 to Emergency Plan Implementing Procedure EPIP-1.01, Emergency Manager Controlling Procedure

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 Page 1 of 8, Rev. 09 and page 6 of 8, Rev.

08; Pages 6 of 39, 7 of 39, 8 of 39 and 9 of 39 of Attachment 1, all Rev. 08.

8402240032 840202 PDR ADOCK 05000280 F

PDR vgv /EMl/17 Enter Pages 1 of 8 and 6 of 8; Pages 6 of 39, 7 of 39, 8 of 39 and 9 of 39 of Attachment 1 all Rev. 10.

Dated 02-02-84

/

\\

. \\

NO. 9?887230 REV:A NUMBER EPIP-l.01 PURPOSE e

e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE PROCEDURE TITLE EMERGENCY MANAGER CONTROLLING PROCEDURE (With 1 Attachment)

REVISION 10 PAGE 1 of 8 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 REV. 06 PAGE(S): 1 of 8 and 4 of 8 REV. 07 PAGE(S): 1 Of 8, Att. 1 page 13 of 39 REV. 08 PAGE(S): 1, 5, 6 & 8; Att. 1, pgs. 2 through 13, 15, 17, 18, 20, and 23 through 38 REV.

1 of 8 and 5 of 8 REV.

1, 6* Att. 1, pgs. 6, 7, 8 and 9 QC REVIEW

~'~

APPROVED

~J~,v,_

OcHAl~~~N STATION NUCLEAR SAFETY ANO OPERATING COMMITTEE DATE:03-10-83 DATE:03-11-83 DATE:03-17-83 DATE: 11-10-83 DATE:01-13-84 DATE: FEB O 2 1984 DATE EB**2.

1984

No, 978.8.7210 0

NUMBER 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

' \\

i No. 97887220 e

NUMBER EPIP-1.01 ATTACHMENT 1

CONDITION/

APPLICABILITY

1.

Safety Limit-RCS Temperature/Pressure curve exceeded POWER & HSB

2.

RCS overpressure ALL CONDITIONS

3.

Rx overpower POWER

4.

RCS leak rate exceeds 300 gpm ABOVE CSD CONDITION

5.

RCS leak rate exceeds 50 gpm ABOVE CSD CONDITION e

ATTACHMENT TITLE EMERGENCY ACTION LEVEL TABLE (TAB B)

REACTOR COOLANT SYSTEM EVENT INDICATION Limits of T.S. Fig.

2.1 EXCEEDED 2735 psig RCS Pressure limit-EXCEEDED 118% Rx thermal power limit -

EXCEEDED EP-2.00, Loss of Reactor Coolant - IMPLEMENTED AND Pressurizer level can not be maintained with two (2)

Charging/SI Pumps in operation Unit in HSD or lower cond-ition as a result of actions required IAW AP-16, Excessive Primary Plant Leakage AND RCS inventory balance indi-cates leakage-GREATER THAN 50 gpm REVISION 10 PAGE 6 of 39 CLASSIFICATION Notification of Unusual Event Notification of Unusual Event Notification of Unusual Event Site Area Emergency Alert

i e

No,97~l!7220 NUMBER ATTACHMENT TITLE EPIP-1.01 ATTACHMENT EMERGENCY ACTION LEVEL TABLE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT CONDITION/

APPLICABILITY

6.

RCS leak rate requiring plant shutdown IAW T.S. 3.1.C POWER & HSB

7.

RCP locked rotor leading to fuel dam-age POWER INDICATION Unit in HSD or lower as a result of any of the following:

a) Unidentified RCS leakage-GREATER THAN.!_ gpm OR b) Identified leakage-GREATER THAN.!£. gpm OR c) Non-isolable fault of RCS pressure boundary All the following exist:

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

AND b) RCP trip caused by Phase Overcurrent Relay - ACTUATION AND c) High Range Letdown Radiation Monitor indication increases5 to-GREATER THAN 5x10 cpm REVISION 10 PAGE 7 of 39 CLASSIFICATION Notification of Unusual Event Alert

' \\~...__....

• No.978~7220

.e e

NUMBER ATTACHMENT TITLE EPIP-1.01 EMERGENCY ACTION LEVEL TABLE ATTACHMENT (TAB B) 1 REACTOR COOLANT SYSTEM EVENT CONDITION/

APPLICABILITY

8.

Gross Primary to Secondary leakage with loss of offsite power ABOVE CSD CONDITION

9.

Excessive Primary to Secondary leakage with loss of offsite power ABOVE CSD CONDITION INDICATION EP-4.00, Steam Generator Tube Rupture -

IMPLEMENTED with SI in progress 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 Unit in HSD or lower condition as a result of actions required by T.S.

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

REVISION 10 PAGE 8 of 39 CLASSIFICATION Site Area Emergency Alert

/

{

\\

\\

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 Secondary leakage ABOVE CSD CONDITION

11.

Primary to Secondary leakage-GREATER THAN 1 gpm ABOVE CSD CONDITION

12.

Loss of 2 of 3 fission product barriers with potential loss of 3rd barrier ALL CONDITIONS EP-4.00, Steam Generator Tube Rupture -

IMPLEMENTED with SI in progress AND Condenser Air Ejector Exhaust - DIVERT to Containment Unit in HSD or lower con-dition as a result of actions required by T.S.

3.1.C.6 Any two of a),b) or c) exist and the third is imminent a) Fuel clad integrity fail-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:

Alert Notification of Unusual Event General Emer-gency

e GOV 02-54 VIRGINIA ELECTRIC AND PowER COMPANY R:ICHMOND, V:IRG:IN.IA 23261 February 17, 1984 Mr. James P. O'Reilly Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

REVISIONS TO Serial No. 081 NO/REB/vgv:EMl-17 Docket Nos. 50--280 50-281 License Nos. DPR-32 DPR-37 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.

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)

Sincerely,

\\

(_

\\

\\_;_l, \\~-

w. L. Stewart