ML040760092

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Rev. 1 to EPIP - 4.35
ML040760092
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 03/08/2004
From: Jennifer Davis
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
04-130
Download: ML040760092 (15)
v • d • e


Text

VIRGINIA ELECTRIC AND POWENZ COMPANY RIcIIMOND, VIRGINIA 23261 March 8, 2004 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Serial No.

NAPS/MPW Docket Nos.

License Nos.04-130 50-338/339 NPF-4/7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 REVISIONS TO EMERGENCY PLAN IMPLEMENTING PROCEDURE Pursuant to 10 CFR 50.54(q), enclosed is a recent revision to the North Anna Power Station Emergency Plan Implementing Procedure. This revision does not implement actions that decrease the effectiveness of our Emergency Plan. The Emergency Plan and Implementing Procedures continue to meet the standards of 10 CFR 50.47(b).

Please update your manual by performing the actions described in Attachment 1, Tabulation of Changes.

Very truly yours, Commitments Stated or Implied: None.

Enclosures cc:

U.S. Nuclear Regulatory Commission (2 copies)

Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 Mr. M. T. Widmann NRC Senior Resident Inspector North Anna Power Station P564.

... 1

ATTACHMENT 1 TABULATION OF CHANGES VIRGINIA ELECTRIC AND POWER COMPANY REVISIONS TO NORTH ANNA POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE Enclosed is a recent revision to the North Anna Power Station Emergency Plan Implementing Procedure (EPIP). Please take the following actions in order to keep your manual updated.

Emergency Plan Privacy and Proprietary Material has been removed. Reference Generic Letter No. 81-27.

-r DATE: 2004-03-02 PAGE: 1 I

NORTH ANNA POWER STATION I

LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMIS FOR LATEST DOCUMENT INFORMATION DOCUMENT NUMBER P-_______.__________

EPIP-1.02 EPIP-1.02 EPIP-1.03 EPIP-1.04 EPIP-1.05 EPIP-1.06 EPIP-2.01 EPIP-2.02 EPIP-3.02 EPIP-3.03 EPIP-3.04 EPIP-3.05 EPIP-4.02 EPIP-4.02 EPIP-4.03 EPIP-4.04 EPIP-4.05 EPIP-4.06 EPIP-4.07 EPIP-4.08 EPIP-4.09 EPIP-4.10 EPIP-4.13 REV 039 011 014 014 016 004 025 015 021 013 015 002 020 015 011 009 009 009 014 015 015 011 009 APPROVAL NNDATE**

01/15/04 09/07/99 09/07/99 09/07/99 09/07/99 09/05/01 08/13/02 08/13/02 03/04/03 03/04/03 07/14/98 04/02/03 06/24/03 06/24/03 12/20/93 11/21/94 01/28/00 12/21/95 09/29/00 12/17/03 12/17/03 08/13/02 09/29/00 EFFECTxx

    • DATE*

01/15/04 10/01/99 10/01/99 10/01/99 10/01/99 09/05/01 08/28/02 08/28/02 03/17/03 03/17/03 07/20/98 04/08/03 07/01/03 07/01/03 01/01/94 11/28/94 02/04/00 12/28/95 10/06/00 02/12/04 02/12/04 08/28/02 10/06/00 DOCUMENT TITLE EMERGENCY MANAGER CONTROLLING PROCEDURE RESPONSE TO NOTIFICATION OF UNUSUAL EVENT RESPONSE TO ALERT RESPONSE TO SITE AREA EMERGENCY RESPONSE TO GENERAL EMERGENCY PROTECTIVE ACTION RECOMMENDATIONS NOTIFICATION OF STATE AND LOCAL GOVERNMENTS NOTIFICATION OF NRC ACTIVATION OF TECHNICAL SUPPORT CENTER ACTIVATION OF OPERATIONAL SUPPORT CENTER ACTIVATION OF LOCAL EMERGENCY OPERATIONS FACILITY AUGMENTATION OF EMERGENCY RESPONSE ORGANIZATION RADIOLOGICAL ASSESSMENT DIRECTOR CONTROLLING PROCEDURE RADIATION PROTECTION SUPERVISOR CONTROLLING PROCEDURE DOSE ASSESSMENT TEAM CONTROLLING PROCEDURE EMERGENCY PERSONNEL RADIATION EXPOSURE RESPIRATORY PROTECTION AND KI ASSESSMENT PERSONNEL MONITORING AND DECONTAMINATION PROTECTIVE MEASURES INITIAL OFFSITE RELEASE ASSESSMENT SOURCE TERM ASSESSMENT DETERMINATION OF X/Q OFFSITE RELEASE ASSESSMENT WITH ENVIRONHENTAL DATA

T DATE: 2004-03-02 PAGE:

2 1-NORTH ANNA POWER STATION LIST OF NAPS EMERGENCY PLAN IMPLEMENTATION PROCEDURES CHECK DMis FOR LATEST DOCUMENT INFORMATION DOCUMENT NUMBER EPIP-4.14 EPIP-4.15 EPIP-4.16 EPIP-4.17 EPIP-4.18 EPIP-4.21 EPIP-4.24 EPIP-4.26 EPIP-4.28 EPIP-4.30 EPIP-4.31 EPIP-4.33 EPIP-4.34 EPIP-4.35 EPIP-5.01 EPIP-5.03 EPIP-5.04 EPIP-5.05 EPIP-5.07 EPIP-5.08 EPIP-5.09 EPIP-6.01 REV 007 011 015 016 013 008 013 012 007 005 003 003 003 001 011 016 010 013 012 008 004 007 APPROVAL XNDATE6*

12/20/93 02/18/00 12/13/02 12/13/02 12/13/02 12/20/93 04/02/03 06/24/03 01/09/97 04/05/02 06/20/94 11/28/00 12/13/02 02/26/04 12/11/96 02/18/00 03/04/03 06/25/96 06/24/03 04/02/03 08/02/02 05/12/99 EFFECTMJ

    • DATEE3 01/01/94 02/28/00 12/18/02 12/18/02 12/18/02 01/01/94 04/08/03 07/01/03 01/14/97 04/09/02 06/20/94 11/30/00 12/18/02 03/02/04 12/17/96 02/28/00 03/17/03 07/02/96 07/01/03 04/08/03 08/15/02 05/17/99 DOCUMENT TITLE INPLANT MONITORING ONSITE MONITORING OFFSITE MONITORING MONITORING OF EMERGENCY RESPONSE FACILITIES MONITORING OF LEOF EVACUATION AND REMOTE ASSEMBLY AREA MONITORING GASEOUS EFFLUENT SAMPLING DURING AN EMERGENCY HIGH LEVEL ACTIVITY SAMPLE ANALYSIS TSC/LEOF RADIATION MONITORING SYSTEM USE OF MIDAS CLASS A MODEL USE OF MIDAS CLASS B MODEL HEALTH PHYSICS NETWORK COMMUNICATIONS FIELD TEAM RADIO OPERATOR INSTRUCTIONS CHEMISTRY SAMPLING TRANSPORTATION OF CONTAMINATED INJURED PERSONNEL PERSONNEL ACCOUNTABILITY ACCESS CONTROL SITE EVACUATION ADMINISTRATION OF RADIOPROTECTIVE DRUGS DAMAGE CONTROL GUIDELINE SECURITY TEAM LEADER CONTROLLING PROCEDURE RE-ENTRY/RECOVERY GUIDELINE

VIRGINIA POWER NORTH ANNA.POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

(With No Attachments)

PAGE 1 of 11 PURPOSE To provide controls for chemistry sampling of the Reactor Coolant System, containment atmosphere and containment sump.

LEVEL 2 COPY THIS DOCUMENT SHALL BE VERIFIED TO A CONTROLLED SOURCE AS REQUIRED TO PERFORM WORK ENTRY CONDITIONS Any one of the following:

1. Alert or higher emergency classification has been declared.
2. Activation by EPIP-4.02, Radiation Protection Supervisor Controlling Procedure.
3. As deemed necessary by the Radiological Assessment Director.

Approvals on File Effective Date 3

+

2

.NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE I1 2 of 11 AHq_

ACTION/EXPECTED RESPONSE F-]

RESPONSE NOT OBTAINED F-

___1 INITIATE EPIP-4.35:

  • By:

Date:

Time:

___2 CHECK WITH RADIATION PROTECTION SUPERVISOR TO ENSURE NORMAL CHEMISTRY SAMPLING IS ACCEPTABLE

___3 CHECK IF SAMPLE POINT IS AVAILABLE IN PRIMARY SAMPLE ROOM IF sampling to be conducted under provisions of the Contingency Plan, THEN GO TO Step 13.

IF sample point is NOT available in primary sample room, THEN determine location of alternate sample point.

NOTE:

Prompt notification of RPS upon detection of stop work dose rates at the Primary Sample Room is essential for timely classification decision-making.

__4 BRIEF SAMPLE PERSONNEL:

a) Review sampling procedure b) Review ingress and egress routes c) Review RWP requirements d) Review enroute hazards e) Review operation of RABBIT sample transfer system f) Review criteria for promptly reporting stop work dose rate

  • 15 R/hr - GENERAL AREA
  • 3 R/hr -

12 INCHES FROM PRIMARY SAMPLE CONTAINER I

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE 3 of 11

_Eq ACTION/EXPECTED RESPONSE H-H RESPONSE NOT OBTAINED F-

___5 DISPATCH SAMPLING PERSONNEL:

a) Assure sampling personnel have proper materials and personal protection equipment b) Give sampling personnel a copy of this procedure

___6 GO TO SAMPLE LOCATION:

a) Use pre-planned travel route to sample location b) Continuously monitor radiation dose rates c) Verify radiation dose rates -

EXPECTED c) IF unexpected radiation dose rates are found, THEN leave area.

CAUTION:

  • Do not open RABBIT transfer system while sending sample.

o Samples may become stuck in the RABBIT system (e.g. due to loss of vacuum). System piping can be monitored to determine the location of the stuck RABBIT. The Radiation Protection Supervisor should be notified if this occurs.

____7 PERFORM SAMPLING:

(STEP 7 CONTINUED ON NEXT PAGE)

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE L~~

4 of 11 I

-ElH ACTION/EXPECTED RESPONSE F-A RESPONSE NOT OBTAINED F-7 PERFORM SAMPLING: (Continued) a) Verify sampling from Primary Sample Room b) Collect required sample volume c) Turn on RABBIT sample transfer system at primary sample room a) IF NOT performing sample from Primary Sample Room. THEN do the following:

1) Perform sampling in designated alternate location.
2) Leave sample area.

a) Monitor sample dose rates.

b) Maintain ALARA (reduce exposure).

c) GO TO Step 7.e.

c) IF NOT operable. THEN do the following:

1) Transfer sample manually in accordance with HP Technician instructions.
2) Leave sample area.

a) Monitor sample dose rates.

b) Maintain ALARA (reduce exposure).

c) GO TO Step 7.e.

d) Send sample to Hot Lab e) Leave sample area by pre-planned route

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE L -

5 of 11

_GA ACTION/EXPECTED RESPONSE

-F-]

RESPONSE NOT OBTAINED F-

___8 PREPARE SAMPLE FOR ANALYSIS:

a) Put sample in a clean poly bag b) Label sample with the following:

  • Date and time
  • Sample type
  • Sample volume

. Dose rate

___9 CHECK SAMPLE ACTIVITY -

LESS THAN 10 mR/HR IF sample activity GREATER THAN 10 mR/hr, THEN do the following:

a) Take sample to Hot Lab for dilution IAW EPIP-4.26. HIGH LEVEL ACTIVITY SAMPLE ANALYSIS.

b) GO TO Step 11.

___10 TAKE SAMPLE TO COUNT ROOM

____11 NOTIFY THE FOLLOWING THAT SAMPLING IS COMPLETE:

. Radiological Assessment Director

  • Radiation Protection Supervisor
  • .Shift Manager 12 GO TO STEP 28

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE 6 of 11

_1EH

'ACTION/EXPECTED RESPONSE F-]

RESPONSE NOT OBTAINED H-NOTE:

CH-94.300, HIGH RADIATION SAMPLING SYSTEM. describes Contingency Plan sampling considerations.

___13 REVIEW SYSTEM DESIGN BASES:

IF sampling is for, THEN consider the following:

Reactor Coolant

  • Design basis RCS estimated sample dose rates:

1000 Rem/hr surface, undiluted OR

- 1 Rem/hr surface, diluted 650 mRem/hr at surface of cask when cover Containment Sump is NOT in place, undiluted

  • Design basis Liquid Sample Panel (LSP) dose rate is 365 mRem/hr at 1 meter
  • LSP is maintained at negative pressure Containment Air
  • CASP design basis dose rates equal 30 mR/hr at three feet
  • Containment Air Sample design basis dose rates:

- 8,000 mR/hr surface

- 100 mR/hr at one foot

  • CASP is maintained at a negative pressure
  • Dose rates and airborne contamination levels at the PCP/CCP are not normally affected by the sampling process

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE 7 of 11 7EAi ACTION/EXPECTED RESPONSE F-]

RESPONSE NOT OBTAINED F-

_ 14 GIVE SAMPLE TEAM COPY OF SAMPLING PROCEDURE(s):

IF sampling is for.

THEN give Sample Team the following:

Reactor Coolant

  • EPIP-4.26, HIGH LEVEL ACTIVITY SAMPLE ANALYSIS Containment Sump
  • 1-OP-12.5. HIGH RADIATION CONTAINMENT SUMP SAMPLING
  • EPIP-4.26. HIGH LEVEL ACTIVITY SAMPLE ANALYSIS Containment Air CH-41.310 (UNIT 1) / CH-42.310 (UNIT 2), HIGH RADIATION SAMPLING SYSTEM CONTAINMENT AIR SAMPLING

NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE L~8 of 11 STPACT ION/EXPECTED RESPONSE HRESPONSE NOT OBTAINED

.__15 BRIEF SAMPLE TEAM:

a) Review sampling and analysis procedures, as appropriate b) Establish and review entry and exit routes (use ALARA) c) Review RWP requirements for sample locations (e.g.. PCP, LSP, PCP/CCP, CASP. as appropriate):

  • Stay times
  • Protective clothing
  • Dosimetry
  • Respiratory equipment
  • Monitoring d) Review criteria for promptly reporting stop work dose rate e) Review cautions:
  • High radiation levels
  • High activity sample level(s)

(for Containment Air samples, estimate the correct volume of sample to be collected using the gas sampler (RCT))

- Open valves slowly f) Give team a copy of this procedure

___16 HAVE SAMPLE TEAM DRESS OUT IAW RWP

__17 NOTIFY RPS THAT SAMPLE TEAM IS READY FOR DISPATCH

,1 NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE I

9 of 11 EAH ACTION/EXPECTED RESPONSE F-A RESPONSE NOT OBTAINED F-

___18 ASK RPS FOR CURRENT PLANT STATUS

___19 GIVE UPDATE TO TEAM MEMBERS

___20 DISPATCH SAMPLE TEAM

___21 CHECK SAMPLE - CONTAINMENT AIR IF Reactor Coolant or Containment Sump sample, THEN GO TO Step 26.

___22 VERIFY SAMPLE PREPARED FOR TRANSPORT:

a) Sample container labelled with the following information:

  • Sample ID and Unit #
  • Sample volume
  • Date and time
  • Dose rate b) Glass bottle and syringe assembly put in separate bags/containers

___23 CHECK SAMPLE CONTACT READING -

LESS THAN 10 MR/HR IF sample contact reading GREATER THAN 10 mR/hr, THEN have HP initiate EPIP-4.26, HIGH LEVEL ACTIVITY SAMPLE ANALYSIS.

Il NUMBER PROCEDURE TITLE REVISION EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE 10 of 11 I I

-ED4 ACTION/EXPECTED RESPONSE I

I RESPONSE NOT OBTAINED I-

___24 TAKE SAMPLE TO COUNT ROOM:

a) Use pre-planned route b) Monitor radiological conditions during transit c) Check dose rates along route within expected levels c) Do the following:

1) Notify RPS.
2) Identify route of lowest dose.

d) Maintain ALARA

___25 GO TO STEP 27

___26 HAVE REACTOR COOLANT SAMPLE ANALYZED:

a) Refer to EPIP-4.26..HIGH LEVEL ACTIVITY SAMPLE ANALYSIS, for sample dilution b) Transport sample to Hot Lab or HRSS hood for dilutions c) Implement appropriate Chemistry procedure for analysis d) Check if diluted HRSS sample is to be flushed back through system for disposal e) Implement affected unit HIGH RADIATION SAMPLING SYSTEM SAMPLE DISPOSAL OR STORAGE procedure Unit 1 -

CH-41.820 Unit 2 -

CH-42.820 d) GO TO Step 27.

NUMBER PROCEDURE TITLE REVISION C,

EPIP-4.35 CHEMISTRY SAMPLING 1

PAGE 11 of 11 WACTION/EXPECTED RESPONSE HRESPONSE NOT OBTAINED

___27 NOTIFY THE FOLLOWING INDIVIDUALS ONCE SAMPLING HAS BEEN COMPLETED:

. Radiation Protection Supervisor

  • Shift Manager
  • Station Emergency Manager

___28 TERMINATE EPIP-4.35:

  • Give completed EPIP-4.35, forms and other applicable records to the Radiation Protection Supervisor
  • Completed by:

Time:

Date:

-END-

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