ML19352A138

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Forwards Suppl to 800916 Request for Revisions to Tech Specs Re post-accident Monitoring Instrumentation & Administrative Controls,Per Category a Lessons Learned Requirements.Info Provides Addl Clarifications W/O Changing Technical Content
ML19352A138
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 03/09/1981
From: Utley E
CAROLINA POWER & LIGHT CO.
To: Ippolito T
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578 NO-81-421, NUDOCS 8103110424
Download: ML19352A138 (6)


Text

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Carolina Power & Light Company March 9, 1981 File: NG-3514(B)

Serial No.: NO-81-421 Office of Nuclear Reactor Regulation W

D ATTENTION:

Mr. T. A. Ippolito, Chief p

Operating Reactors Branch No. 2 S'

United States Nuclear Regulatory Commission D

9 Washington, D. C.

20555

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S BRUNSWICK STEAM ELECTRIC PLANT UNIT NOS. 1 AND 2 p

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DOCKET NOS. 50-325 AND 50-324 4

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LICENSE NOS. DPR-71 AND DPR-62 e

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REVISIONS TO THE REQUEST FOR LICENSE AMENDMENT -

CATEGORY "A" LESSONS LEARNED ITEMS

Dear Mr. Ippolito:

As discussed in telephone conversations with your staff, Carolina Power & Light Company (CP&L) herewith submits the attached revisions to eupplement its September 16, 1980 request for revisions to the Technical Specifications and Operating Licenses for the Brunswick Steam Electric Plant (BSEP) Unit Nos. 1 and 2, concerning Category "A" Lessons Learned items.

The attached revised pages provide additional clarification only and do not change the technical content of the previous submittal. These attached pages should replace the corresponding pages of CP&L's September 16, 1980 request.

If you have any questions on this revision, please contact our staff.

Yours very truly,

, jy dL E.'E. Utley Executive Vice President Power Supply and Engineering & Construction-JHE/je (100-000)

Attachments cc:

Mr. J. P. O'Reilly (NRC-RII)

- Sworn to and subscribed before me this ' 9th day of March 1981 f

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411 Fayetteville Street

  • P. O. Box 1551
  • Raleigh, N. C. 27602
  • O3110919

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TABLE 3.3.5.3-1

+

POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.

OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS i

1.

Reactor vessel water level 2

(B21-LITS-N026A, B; B21-LR-615; B21-LI-R604A, B and B21-LITS-NO37) 2.

Reactor vessel pressure 2

(B21-PI-R004A, B; C32-LPR-R608 and C32-PT-N005A, B) 3.

Containment pressure 2

(CAC-PI-2599; CAC-PT-2559; CAC-PR-1257-1 and CAC-PT-1257-1) 4.

Containment pressure 2

(CAC-TR-1258-1 through 13, 22, 23, 24 and C91-P602) 5.

Suppression chamber atmosphere temperature 2

(CAC-TR-1258-17 through 20 and C91-P602) 6.

Suppression chamber water level 2

(CAC-LI-2601-3; CAC-LA-2602; CAC-LT-2601; CAC-LT-2602 and CAC-LY-2601-1) 7.

Suppression chamber water temperature 2

(CAC-TR-1258-14, 21 and C91-P602) 8.

Containment. radiation 2

(CAC-AR-1260; CAC-AQH-1260-1, 2, 3; CAC-AR-1261; CAC-AQH-1261-1, 2, 3; CAC-AR-1262'and CAC-AQH-1262-1, 2, 3) 9.

Ccatainment oxygen 2

(CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263) 1 10.

Containment-hydrogen 2

(CAC-AT-1959-1; CAC-AR-1259; CAC-AT-1263-1 and

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CAC-AR-1263) 11.

Safety relief valve position indication:

1/ valve Primary

-Sonic (B21-FY-4157 through 4167)

Secondary - Temp. (B21-TR-R614 points 1-11)

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BRUNSWICK-UNIT 1:

3/4 3-51 Amendment No.

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1

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MINIMUM SHIFT CREW COMPOSITION!

Conditior, of Unit 1

.dnit 2 in CONDITION 1, 2 or 3

,. s

. LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 l

4&5 SOL **

2 2*

OL**

3 2

Non-Licensed i

4 h

3 i,

Shift Technical Advisor 1

0 Condition of Unit 1 - Unit 2 in CONDITION 4 or 5 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL **

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2 1*

l l

OL**

3 2

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Non-Licensed

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3 l

3 Shift Technical Advisor' 1

n Condition of Unit 1 - No Fuel in Unit 2

.i LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SOL 1

1*

OL 2

1 Non-Licensed 2

1 Shift Technical Advisor 1

0 Does not include the licensed Senior Reactor Operator. or Senior Reactor

=

Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.

    • Assumes each individual is licensed on both plants f Shift crew composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accomodate unexpected absence of on duty shif t crew members provided imediate action is taken to restore the shift crew composition to within the mini =um requirements of Table 6.2.2-1.

e ERU :S*.!!CK-UNIT 1 6-5 Amendment No.

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TABLE 3.3.5.3-1 POST-ACCIDENT MONITORING INSTRUMENTATION MINIMUM NO.

OF OPERABLE INSTRUMENT INSTRUMENT AND INSTRUMENT NUMBER CHANNELS

.1.

Reactor vessel water level 2

(B21-LITS-NO26A, B; B21-LR-615; B21-LI-R604A, B and B21-LITS-N037) 2.

Reactor vessel pressure 2

(B21-PI-R004A, B; C32-LPR-R608 and C32-PT-N005A, B) 3.

Containment pressure 2

(CAC-PI-2599; CAC-PT-2559; CAC-PR-1257-1 and

'CAC-PT-1257-1) 4.

Containment pressure 2

(CAC-TR-1258-1 through 13, 22, 23, 24 and C91-P602) 5.

Suppression chamber atmosphere temperature 2

(CAC-TR-12.,8-17 through 20 and C91-P602) 6.

Suppression chamber water level 2

(CAC-LI-2601-3; CAC-LA-2602; CAC-LT-2601; CAC-LT-2602 and CAC-LY-2601-1) 7.

Suppression chamber water temperature 2

(CAC-TR-1258-14, 21 and C91-P602) 8.

Containment radiation 2

(CAC-AR-1260; CAC-AQH-1260-1, 2, 3; i

CAC-AR-1261; CAC-AQH-1261-1, 2, 3;_

'CAC-AR-1262 and CAC-AQH-1262-1, 2, 3) l

-9.

Containment oxygen 2

l (CAC-AT-1259-2; CAC-AR-1259; CAC-AT-1263-2 and CAC-AR-1263) l 10.

Containment hydrogen 2

'f (CAC-AT-1959-1; CAC-AR-1259; CAC-AT-1263-1 and CAC-AR-1263) l-11.

Safety relief valve position indication:

1/ valve Primary - Sonic (B21-FY-4157 through 4167)

Secondary - Temp. (B21-TR-R614 points 1-11) i BRUNSWICK-UNIT 2 3/4 3-51 Amendment No.

YABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITIONi Condition of Unit 1 - Unit 2 in CONDITION 1, 2 or 3 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 SQL**

2 2*'

OL**

3 2

Non-Licensed 4

3 Shift Technical Advisor 1

0 Condition of Unit 1 - Unit 2 in CONDITION 4 or 5 l

LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1, 2, 3 4&5 50L**

2 1*

OL+*

3 2

Non-Licensed 3'

3 5

Shift Technical Advisor 1

1 0

{

Condition of Unit 1 - No. Fuel in Unit 2 LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 50L 1

1*

OL 2

1 l

Hon-Licensed 2

1 l

Shift Technica1' Advisor 1

0

  • Does not incluoe the licen' sed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.
    • Assumes each individual is licensed cni both plents.

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! Shift crew composition, including an individual qualified in radiation

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protection procedures, may be less than the minimum requirements

(:

for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to acco.:modate-unexpected absence of on duty shift crew members provided immediate 1

action is taken to _ restore the shift crew composition to within the minimum requirements of Table 6.2.2-1.

BRUNSWICK-UNIT 2 6-5 Amendment No.

6 m

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,O ADMINISTRATIVE CONTROLS (h

6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the unit staf f shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the (Radiation Protection Manager) who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shif t Technical Advisor who shall have a bachelor'c degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidente 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet er exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix '.'A" of 10 CFR Part 55.

6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Fire Chief and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 1

6.5 REVIEW AND AUDIT 6.5.1 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)

(h FUNCTION 6.5.1.1 The PNSC shall functionI to advise the General Manager on all matters related to nuclear safety.

COMPOSITION 6.5.1.2 The PNSC shall be composed of the:

Chairman:

Plant General Manager Vice Chairman:

Operations Manager, Maintenance Manager, Technical - Administrative Manager or Director-Nuclear Safety and QA Secretary:

Administrative Supervisor Member:

Maintenance Supervisor (I&C)

Member:

Maintenance Supervisor (Mechanical)

Member:

Engineering Superviso,r

^

Member:

Environmental and Radiation Control Supervisor Member:

Quality Assurance Supervisor Member:

Shift Operating Supervisors Member:

Training-Supervisor ALTERNATES

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6. 5.1.'3 All alternate members shall be appointed in writing by the PNSC Chairman ta serve on a temporary" basis; however, no more than two alternates shall participate as voting members in PNSC activities at any one time.

BRUNSWICK - UNIT 2 6-6 Amendment No.

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