ML20050D402

Tech Spec 3.1.3.7 Requiring Documentation of All Control Rod Reed Switch Failures

ML20050D402
Person / Time
Site:	Brunswick
Issue date:	04/07/1982
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20050D399	List: ML20050D396 ML20050D402
References
NUDOCS 8204120181
Download: ML20050D402 (4)

Text

,

REACTIVITY CONTROL SYSTEMS CONTROL R00 POSITION INDICATION LIMITING CONDITION FOR OPERATION 3.1.3.7 All control rod reed switch position indicators shall be OPERABLE.

APPLICABILITY: CONDITIONS 1, 2 and 5*.

ACTION:

a. In CONDITION 1 or 2:

1. With one or more control rod reed switch position indicators inoperable, except for " Full-in" or " Full-out" indication, the provisions of Specification 3.0.4 are not applicable i

and operation may continue, provided that within one hour:

a) The position of the control rod is determined by an alternate method, or b) The control rod is moved to a position with an OPERABLE reed switch position indicator, or c) The control rod with the inoperable reed switch position indicator is dc lared inoperable and the requirements of Specification 3.1.3.1 are satisfied; Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

d) If there are at least 45 of the 00 to 48 position reed switches operabic, including the switches immediately to either side of an inoperable reed switch and the appropriate' action in Specification a.1 above is taken, then no report per Specification 6.9.1.9 is required.

(Refer to Specification 6.9.1.5.1)

2. With one or more control rod reed switch " Full-in" and/or

" Full-out" position indicators inoperable, the affected control rod may be bypassed in the Rod Sequence Control System, the provisions of Specification 3.0.4 are not applicable and operation may continue, provided; a) The actual control rod position is known, b) The affected control rod is moved to the correct position in the proper sequence, and c) Each bypassed control rod is separated in all direc-tions from any other bypassed control rod by at least two control cells.

b. In CONDITION 5* with a withdrawn control rod reed switch posi-tion indicator inoperable, fully insert the withdrawn control rod. The provisions of Specification 3.0.3 are not applicable.

• At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

$$[k$o 0 3/4 1-11 P

T REACTfVITY CONTROL SYSTEMS CONTROL R00 p0SITION INDICATION LIMIT'.NG CONDITION FOR OPERATION i

2.1.3.7 All control rod reed switch position indicators shall be OPERABLE.

J APPLICABILITY: CONDITIONS 1, 2 and 5*,

l ACTION:

a. In CONDITION 1 or 2:

l. With one or more control rod reed switch position indicators j inoperable, except for " Full-in" or " Full-out" indication, l the provisions of Specification 3.0.4 are not applicable and operation may continue, provided that within one hour:

l 1 a) The position of the control rod is determined by an  ;

j alternate method, or i

i b) The control rod is moved to a position with an OPERABLE reed switch position indicator, or ,

! c) The control rod with the inoperable reed switch J

position indicator is declared inoperable and the requirements of Specification 3.1.3.1 are satisfied; ',

Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

d) If there are at least 45 of the 00 to 48 position reed i

switches operable, including the switches immediately to either side of an inoperabic reed switch and the appropriate action in Specification a.1 above is.taken,

, then no report per Specification 5.9.1.9 is required.' '

j (Refer to Specification 6.9.1.5.1)

With one or more control rod reed switch " Full-in" and/or

2. ,

" Full-out" position indicators inoperable, the affected -

control rod may be bypassed in the Rod Sequence Control System, the provisions of Specification 3.0.4 are not applicable and operation may continue, provided; a) The actual control rod position ~ is known, b) The affected control rod is moved to the correct position in the proper sequence, and

! c) Each bypassed control rod is separated in all direc-l tions from any other bypassed control rod by at least two control cells.

• At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2. '

i BRUNSWICK - UNIT 2 3/4 1-11

. ADMINISTRATIVE CONTROLS START-UP REPORT (Continued) completion of start-up test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS 1/

6.9.1.4 Annual reports covering the activities of the unit as described below

during the previous calendar year shall be submitted prior to March 1 of each year. Tha initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include a tabulation of the number of statioit, utility, and other personnel (including contractors) 4 receiving exposures greater than 100 mrem /yr a their associated man rem exposure according to work and job functions, g; e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be ausigned to specific major work functions.

6.9.1.5.1 An annual report is made to comply with 10CFR50.59. This report shall include a listing of:

a. All control rod reed switch failures not previously reported per Specification 3.1.3.7.a.1.d.

b. All SR/V challenges.

MONTHlX OPZRATING REPORT 6.9.1.6 Ro'utine reports of operating statistics and shutdown experience shall be sube.itted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear. Regulatory Commission, Washington, D.C. 20555, with a copy to the i Regional Office, to arrive no later than the tenth of each month following the

_ calendar month covered by the report.

i REPORTABLE OCCURRENCES r

6.9.1.7 The ' REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6 9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee' event report shall be completed and reference shall be made to the original report date.

i l

1/~ A single submittal may be made for a multiple unit station. The submittal

~~

should combine those sections that are common to all units at the station.

i j2/ This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20.

l BRUNSWICK - UNIT 1 6-16

DMINISTRATIVE CONTROLS START-UP REPORT (Continued) s completion of start-up test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL PEPORTSil 6.9.1.4 Annual reports covering the activities of the unit as described below

,during the previous calendar year shall be submitted prior to March 1 of each year.- The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annuni basis shall include a tabulation of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr a their associated man rem exposure according to work and job functions, g; e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Sm' a ll exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

6.9.1.5.1 An annual report is made to comply with 10CFR50.59. This report

~

shall include a listing of:

a. All control rod,rced switch failures not previously reported per Specification 3.1.3.7.a.1.d.

b. All SR/V challenge's.

MONTHLY OPERATING REPORT 4

6.9.1.6 Routine: reports of operating statistics and shutdown experience shall b: submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Ol*fien, to arrive no later than the. tenth of each month following the calendar month covered by the report.

REroRTABLE OCCURRENCES

-69.1.7 . The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be y made to the original report date.

If A , single submittal may be made for a multiple unit station. The submittal should coabine those sections that are common to all units at the station.

j[/ This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20.

i BRUNSUICK - UNIT 2 6-16

. - , - . -