IR 05000270/1973001

From kanterella
Jump to navigation Jump to search
Insp Rept 50-270/73-01 on 730117-19 & 29-30.No Noncompliance Noted.Major Areas Inspected:Status of Plant Sys Testing,Review of Test & Instrument Procedures & Minutes from Station Review Committee 1972 Meetings
ML19317D354
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 02/13/1973
From: Jape F, Murphy C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19317D351 List:
References
50-270-73-01, 50-270-73-1, NUDOCS 7911270573
Download: ML19317D354 (7)


Text

{{#Wiki_filter:- . . O @D[ e~ 7-; I

" , c,g UNITED STATES . ATOMIC ENERGY COMMIS510N - ' DIFIOTCPATI CF F23U*ATC.TY CPIPATIC.':3 - '~- /J aes ou o - sv.-c va %g j# 2x p e.:-r a c e sv a r e r.. = -a cs- ,,,,,,, ,,,,,,,,,,, en v arwa~r4.cecacia xm s l

l R0 Inspection Report No. 50-270/73-1 Licensee: Duke Power CompsLy Power Building 422 South Church Street Charlotte, North Carolina 28201 Facility Nane: Oconee Unit 2 Docke': N'o.: 30-270 Lice. No.: CPPR-34

. Ca c.ry: B1

Iteat Un: Seneca, South Carolina . Type of License: 3&W, PWR, 2452 Mv(t)' - t Type of Inspection: Routine, Unannounced i Dates of Inspection: January 17-19, 1973, and January 29-30,.1973 .. Dates of Previous Inspecticn: Nave:ber 14-17, 1972, and December 12-14, 1972

f Principal Inspector: 4,ata I/ hmL d-/3' 73

F.' Jape, Reacror Inspector Date Facilities Test and Startup Branch Accompanying Inspector: None Other Accompanying Personnel:, None, , [[:[ r,4 / d!/J 75 Reviewed by:~C.E.. Murphy,/ Acting Chief, Facilities Test and Date' StartupBranch./ a 11 pow _ _- - -- _ - .

_ - - _- - -.

. . . . . . . R0 Report No.. 50-270/73-1-2- ' ' .

SUMMARY OF FINDINGS i j I.

Enforcement Action None i ' II.

Licensee Action on Previously Identified Enforcement Matters There are no presiously identified enforcement matters that

are related to the preoperational and initial startup test program.

III.

New Unresolved Items

73-1/1 Test Procedure Index Disaerees With FSAR The test procedure index is not in complete agree =ent j with Tables 13-1 and 13-2 in the FSAR.

(See Details I, paragraph 5.)

i IV.

Status of Previously Reported Unresolved Items . There are no previously reported unresolved items.

l V.

Design Changes ! None i VI.

Unusual Occurrences i I None

VII.

Other Significant Findings None , I VIII.

Management Interview - A management interview was held on January 19, 1973, at the conclusion of the inspection.

The following people were in attendance: Duke Power Company (DPC) J. W. Hampton - Assistant Plant Superintendent R. M. Koehler - Technical Support Engineer M. D. McIntosh - Operating' Engineer , -- i ' e .. - -,,, - .-s.

-w..-g.

m ...,,- +, ,.,.,,-.- . -

  • -

- tq-se f M-( m + = P.

-

  • '

t +m w& ( 1r-

.. .. -. ._.

. .. _ . . _ _. _ _ _. _. _ _ _.- _..

. . _ ~

! , l RO Ra} ort No. 50-270/73-1-3-t D. C. Holt - Assistaat Nuclear Test Engineer . N. A. Rutherford - Junior Staff Engineer L. E. Summerlin - Staff Engineer i The folicwing ite=s were discussed: i

A.

Plant Status for Testing , The status of plant systens that have been turned over to ' ' the Steam Production Depart =ent was reviewed.

(See Details a , I, paragraph 2.)

l B.

Review and Evaluation of Tests and Test Results l The inspector stated that he had reviewed seven test procedures and six instrument procedures.

These procedures were found to b~e

in agreement with DPC's Administrative Policy Manual for Nuclear , } Stations, (APM/NS), and with ANS 3.2, " Standard for Administrative Controls."

(See Details I, paragraph 3.)

l C.

Review of Station Review Co=mittee (SRC) and Nuclear Safety i Review Co=mittee (?!SRC) Activity _ The inspector stated that hc had reviewed-the minutes of the SRC and the NSRC.

The co==ittee activity was fcund to

be as described in the FSAR.

(See Details I, paragraph 4.)

' l D.

Unit 2 Test Procedura Index The inspector stated that he had compared the index of test procedures, instrument procedures and periodic ' ' procedures for Unit 2 with the list of tests presented

in' Tables 13-1 and 13-2 of the FSAR. The two lists are ! not in complete agree ent.

(See Details I, paragraph 5.)

i - i , i s ! ! - ! , p y p l w ' l ' l-l t

>- - -. - .- -.~._ _ _. . _ _. _, -, _.., ,_, m __ _ ~ ,, -, .-- ,,.,--,.n,-, - , -. - - - - -, -, - - - -

- - _ _ _ -. _ _ _ _ _ _ - _. _ _ _.._.

. . - . ! - ,

. RO Report No.~50-270/73-1 I-l L) l DETAILS I Prepared by:. /A4 x h% d '/3' t ' F. Jape Date v J-Reactor Inspector

i } Facilities Test and . j Startup 3 ranch

l l Dates of Inspection: January 17-19, 1973 i and. January 29-30, 1973 /. -<-/ 'M,' ) Reviewed by v b l C. E. Murphy / j/ Date ' ' ! Acting Chief, Facilities ' ' Test and Startup 3 ranch r ) i ' l.

Individuals Contacted '

l Duke Power Cocoany (DPC)

- J. W. Hampton - Assistant Plant Superintendent , R. M. Koehler - Technical Support Engineer

- ] L. E. Su= merlin - Staff Engineer - M. D. McIntosh - Operating Engineer D. J. Rains - Assistant Plant Engineer J. W. Cox - Assistant Plant Engineer 2.

System Turnover from Construction to Steam Production Department

Approximately seventeen systems have been turned over to the Steam j Production Depart =ent for testing.

These syste=s include the following:

-

Borated Water Storage Tank ' High Pressure Injection System , j Core Flood System ' l High Pressure Service Water i i Chemical Addition and Sampling System ,

There are approximately fourteen other systems to be released.

The procedure for transferring and tagging equip =ent and establishing , a control boundary was discussed with the licensee's representative.

The inspector had no questions or co=ments on the procedure.

' 3.

Review of Test Procedures i The following seven test procedures and six instru=ent procedures . '% Nd ! e

q...., = =. ,+w.n-w en g- + ee m,

-'_-*-*e--++-e -**"+4*-** -W" ' ' " * " + '** p , r-r-e- _ w - a --p3-- qq y -- mer y-w

. - . - . ,

.

.. RO Report No. 50-270/73-1 I-2 . were reviewed and the test results evaluated by the inspector.

,The procedure for=at, content and verification of test results was found to be in agreement with Sections 3.2 and 4.4 of DPC's , APM/NS.- The inspector had no questions on these procedures.

, Test Procedures a.

TP 204/4 - RB Spray Perfor=ance Test , b.

TP 250/5 - HPSW Syste= Functional and Operational Test c.

TP 251/4 - RCW Hydro Test d.

TP 251/5 - RCW Flushing Procedure e.

TP 301/3N - RPI and NI Initial Power Application f.

TP 301/1 - Engineered Safeguards Initial Power Application j g.

TP 320/1 - ICS and Auxiliary Control AC Pow *er - Initial Application Instrument Procedures - a.

IP 201/LA - CF Tank Level Instrument Calibration b.

IP 202/lD - E=ergency EPI Flow Instrument Calibration c.

IP 202/lF - Letdown Level Instrument Calibration d.

IP 203/LA - BWST Level Instrument Calibration IP 203/1C - Flow to RV from LP Pump, Flow Instru=ent Calibration i e.

, 4.

Review of SRC and NSRC The membership, meeting frequency and the activities of the SRC and the NSRC were reviewed to determine if these co==ittees are performing as described in the FSAR.

The NSRC (for=erly called GORC) =et six ti=es in 1972 with more than a quorum of = embers.

The activity at these meetings was 's described in a the FSAR.

The SRC =et 74 times in 1972 with a quorum or more members.

The co==1ttee activity consisted pri=arily of reviewing and co==enting , on test and operating procedures as described in the FSAR.

- The inspector had no questions on either of these co==ittees.

5.

General Review of Testing Progra , The inspector compared the licensee's index of preoperational testing with the program described in the FSAR.

, I The following tests are not included in the test index dated October 28, 1972.

The index is revised from time-to-time and the licensee's action , i regarding the missing tests is indicated below.

1.

I

! I ' , -i

i . ..-...., .. - -.. -,... . .,. . - - .

.. ...... ... ^ ::.... .....2.

....:.--.~....-..... .. _ _..

  • :....a. =

. ~ ! - RO Report No. 50-270/73-1 I-3 - . t Test Licensee Action . 1.

Penetration Room Pressure Drop and Filter Test Will add as a TP 2.

liPI Systes Engineered Safeguards Iert Will add as a TP 3.

Integrated Centrol Red Drive System Test Will add as a IP 4.

Control Rod Drive Trip Test Will add as a TP 5.

Electrical System Nor=al and E=ergency Part of this test Operation Test is for Unit 1 only . 6.

Keowee Hydro E=ergency Power Furcti"aal rest Part of this test is for Unit 1 only 7.

Core Flooding 3ystem Engineered Safeguards Test This test is for Unit 1 only 8.

Nuclear Instrumentation Power Calibration Will add as a IP 9.

Xenon Reactivity Worth and Rapid Depletica Test Undecided 10. Nuclear Steam Supply System Heat Salance Undecided Until the questions on all of the above tests are resolved, this iten will be carried as an unresolved item.

6.

Organization The licensee's organization was reviewed and found to be structured as described in the FSAR and in agreement with Criterion I of Appendix 3 to 10 CFR 50.

lhe authorities and responsibilities of each position within the organization are described in the FSAR.

Functionally, the organization is operating as described.

Plant tests, operating and maintenance procedures are being prepared, reviewed and approved as described in the FSAR.

. 7.

Document Control Section 2.1, " Document Control," of the APM/NS and Administrative Procedure No. 1, " Distribution and Control," were reviewed.

The purpose of these procedure.7 is to ensurc that current documents and drawings are used to test, operate and maintain systers and components ' at Oconee.

The procedures provide for the distribution of documents and drawings to plant personnel.

Changes and revisions to documents and drawings are required to be reviewed for adequacy and appropriate approvals are required.

, The procedures are being i=plemented as prescribed and were found to ~ be in agree =ent with Criterion VI of Appendix 3 to 10 CFR 50.

_

  • ...

, . . , . . . , . . RO Report No. 50-270/73-1 I-4 2^ i

</- . , , .. The inspector had no comments or questions regarding these procedures

at this time.

, 8.

Test Control The inspector reviewed the program for initial tests and operation.

Written procedures are provided for test and operation of plant j equipment. The format of tests include the purpose, test conditions, The precautions, limitations, prerequisites and acceptance criteria.

tests reviewed to date by the inspector are in compliance with the FSAR, ANS 3.2, and with Criterion XI of Appendix 3 to 10 CFR 50.

The FSAR requires an analysis of test results to ensure components and ' ', syste=s are perforsing as required by the previously established acceptance criteria.

The inspector noted that results of ccmpleted tests are being evaluated and documented by the licensee. To date, the results from seven test-procedures and six instrument procedures have been reviewed by the inspector.

(See Details I, paragraph 3.)

The inspector had no questions

or cc =ents on the program performance at this time.

. ' %,, I-

a e i

% .

a . F

i l ',. l { %_J q . l


-

_ _ _.. - .. _ _ _ _ _., _ _ _,, _ _ _ _ _ l -.. - . -. _ - . - -, }}