ML20069L850

Proposed Tech Specs Changes Re Generic Ltr 83-02 Concerning NUREG-0737 Items

ML20069L850
Person / Time
Site:	Cooper
Issue date:	04/27/1983
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20069L833	List: ML20069L830 ML20069L850
References
RTR-NUREG-0737, RTR-NUREG-737 GL-83-02, GL-83-2, NUDOCS 8305020464
Download: ML20069L850 (3)

Text

I \

e ~

GEMAC 916.75" - 400" I

IN.

848.75" -332" 850"_ INSTRUPENT TAP 806-75d*-

REACTOR 722.25" VESSEL yJEk D GE FLANGE l

650" 640.0" Mg, _ _

LINE YARWAY GEM C 60d*- BARTON YARWAY 3

Y A R W AY -575.25(8) + 60" 1 -- - - - - - - - - - - - - HPCI 8 : +60"- - - 4 60" 576.7f - + 60" I3 58 8l8 42.5 %HiALARM 552.56"- +206 550"--544.25(4)

_529.25(3) REACTGt -

516.7 5 _g3 0"--- ------

-S C R A,M, ,_ 'dL - 56 0 t

479.75(2) _.37"( 2 ) (9-5)

(-FEED WATM MO INITIATE RCIC, HPCI, ppgy _ _

450',- TRIP RECIRC. PUMPS 400"-

-371.25 (I) -145.5" ( l )

-156 T--INITIATE RHR , C. S., - - - - - . . - 150" 366.75" TAF+ 352.56',-- 0" 350"-- -352. 56', START DIESEL 8 LI-85 UTE Td A.D.S. g}gggg3 e-6")

313 5"---39" ij ( "0I IN STRU M ENT 3Og. 2 RACK 2/3 / ' ( 25 -5 8 25-6 )

CORE HEGHT PERMISSt\E p 252.56"- -100" 250"- @

LI-9i WATER LEVEL NOMENCLATURE (9-3) U 206- 208.56 LEVEL HEIGHT ABCNE INSTRUMENT HT ABOVE R TAF

(- N0ZZLE 17aI.-

161.5" C NO. VESSEL ZERO

( in.)

READING (in.)

150"- 58.5 222.69 N0ZZLE r (8) 575.25 42.5 206.69 (7) 559.25 (4) 544.25 27.5 191.69 10 0"- (3) 529.25 12.5 176.69 (2) 479.75 -37 127.19 (l) 371.25 - 14 5.5 18.69 50"-

d.

E LE VAT 10N 917'-O" VESSEL BO T TO M FIGURE 2.1.1 REACTOR WATER LEVEL INDICATION CORRELATION 8305020464 830427 DR ADOCK 05000298 PDR

, + - - _ - , , _ .

F

1. A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) re-ceiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job ,

functions, 1/ e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special main-tenance (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 totaling 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.

2. A summary desetiption of facility changes, tests or experi-ments in accordance with the requirements of 10CFR50.59(b).

3. Pursuant to 3.8.A, a report of radioactive source leak testing. This report is required only if the tests reveal the presence of 0.005 microcuries or more of removable contamination.

4. Documentation of all challenges to relief valves or safety valves.

D. Monthly Operating Report Routine reports of operating statistics, shutdown experience, and a narrative summary of operating experience relating to safe operation of the facility, shall be submitted on a monthly basis to the individual designated in the current revision of Reg.

Guide 10.1 no later than the tenth of each month following the calendar month covered by the report.

6.7.2 Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, 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.

1/ This tabulation supplements the requirements of $20.407 of 10CFR Part 20.

-231-k

Nots: This itsn is intended to provida for reporting of potentially gtneric problems.

10. Failure or malfunction of the relief valves or safety valves.

l B. Thirty Day Written Reports. The reportable occurrences discussed below shall be the subject of written reports to the appropriate Regional Office within thirty days of occurrence of the event.

The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additiona.1 narrative material to provide complete explanation of the circumstances surrounding the event.

1. Reactor protection system or engineered safety feature instrument settings which are found to be less conserv-ative than those established by the technical specifica-tions but which do not prevent the fulfillment of the functional requirements of affected systems.

2. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation-or plant shutdown required by a limiting condition for operation.

Note: Routine surveillance testing, instrument calibration, or preventative maintenance which require system configurations as described in items 6.7.2.B.1 and 6.7.2.B.2 need not be reported except where test results themselves reveal a degraded mode as described above.

3. Observed inadequacies in the implementation of admin- '

istrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.

4. Abnormal degradation of systems other than those specified in item 6.7.2.A.3 above designed to contain radioactive material resulting from the fission process.

Note: Sealed sources or calibration sources are not included under this item. Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical specifications.need not be reported under this item.

-234-