IR 05000289/1974028

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Insp Rept 50-289/74-28 on 740711-12 & 16-17.No Noncompliance Noted.Major Areas Inspected:Preoperational Test Results, Startup Test Program & Results & Westinghouse DB-50 Reactor Trip Breakers
ML19256D468
Person / Time
Site: Crane Constellation icon.png
Issue date: 08/05/1974
From: Spessard R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML19256D467 List:
References
50-289-74-28, NUDOCS 7910180801
Download: ML19256D468 (10)


Text

{{#Wiki_filter:' ~. ' __ -.z - , U.S. ATC.'!IC ENERGY C01011SSION 1- [\\ DIRECTORATE OF REGULATORY OPERATIONS g O

REGION I

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, s.=.. e.. . RO Inspection Report No: 50-289/74-b8 Docket No: 50-289

==5=1 EEh r Licensee: Metrocolitan Edison Coenany License No: DPR-50 j~? 3= _ -. . Three Mile Island Unit I Priority: _--- gt B-2 Category: Location: Middletcun, Pennsylvania . _ ' .

== Typ'e of Licensee: PWR 871 We (B&W)

Type of Inspection: Routine, Announced = Dates of Inspection: July 11, 12, 16 and 17, 1974 es of Previous Inspection: Ju y 11-12, 1974

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. /C [ MM,wg _ p- _ Reporting Inspector: ' Da te ' ~ R. L. Spessard, Rdctor Inspector Acconpanying Inspectors: ,., g Date Date Date . -. . . ~ Date

, . Other Accompanying Personnel: None Dn:c _.g .. ':"

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Reviewed By: A. B.' Davis, Senior Reactor Inspector, 'Da t e $3:5

G, , " ". = Reactor Operations Branch

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SUMMARY OF FINDICS

-... - -.. Enforcement Action . _T.z::: A.

Violations [ 27 g . None Identified y.}~-~ : qu:r u B.

Safety Items ... None Identified g 52Ei Licensee Action on Previousiv Identified Enforcement Items .. _., l:ss Not Inspected

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Unusual Occurrences done Identified

== Other Significant Findines - - g: A.

Current 1.

Initial startup testing through the 40% FP plateau has been 5I ccepleted, and the data has been evaluated and accepted by-the licensee. RO:I review of this data and the licensee's evalua-tion disclosed no deficiencies.

(Details, Paragraph 3) i 'r::

Testing at the 76% FP plateau was in progress.

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Status of Previousiv Reoorted Unresolved Ite=s Not Inspected . _ .= Management Interdev ' An exit interview was held on site on July 17, 1974 at the conclusion - of the inspection with Mr. J. Herbein, Met Ed Station Superintendent and Mr. G. Miller, GPU Test Superintendent. The following su=marizes the ,. items discussed:

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Preoperational Test Resul.s (Details, Paragraph 2) =] .. B.

Initial Startup Test Procedures and Results (Details, paragraph 3) .x;J g c.

westinghouse DB-so Reactor Trip Breakers (Details, Paragraph 4) 1449 250 _ =- . _ ._ ~ ......

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Makeup Pu=p Bypass Orifices The inspector was informed that 2 of the 3 orfices of improved 7" design * were beginning to.show evidence of erosion, as determined iQ during weekly radiography examinations.

The erosion was character- ~J ized as slight, and the licensee stated this matter was being ~%=_.= monitored closely. Additionally, the inspector was informed -~ that RO:I would be kept informed on this matter.

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Environ = ental Incident The inspector was informed that the PORC was investigating a matter that may be reportable pursuant to the. Environ = ental Technical

. Specifications. The matter related to operability of' temperature.

monitoring equipment for river water and plant river discharge and the possibility of exceedi'ng the 30F negative te=perature differen-tial limit. The licensee stated RO:r would Fe Eept informed on'thi's matter. ** -~w:;_;. '

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  • Licensee letter dated June. 10, 1974 (A0 74-5)
    • Subsequently Reported as EI 74-8 (Telegram dated July 19, 1974 and Letter dated July 24, 1974)

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== DETAILS c , I, , -..:.- 1.

Persons Contacted ' ' ly , l$ D =H: ' ' Di

== l rr . Metrocolitan Edison Comoany n --- a . Mr. J. Herbein, Station Superintendent gg:5 Mr. J. Colitz, Station Engineer f= Mr. J. Floyd, Supervisor of Operations Mr. J. O'Hanlon, Nuclear Engineer Mr. W. Potts, Supervisor of Quality Control Mr. M. Ross, Shif t Supervisor =:=.... General Public Utilities Service Corporation .. =. Mr. J. Barton, Startup and Iest Manager Mr. G. Miller. Test Superintendent Pz. R. Toole, Assistant Test Superintendent '= Mr. M. Nelson, Technical Engineer Mr. W. Behrle, Shift Test Director '- Mr. C. Gato, Shif t Test Engineer -

Mr. T. Hawkins, Shif t Test Engi~neer Babcock and Wilcox Nuclear Services .. _. . Mr. J. Flint, Shift Data Analyst Mr. W. Raymond, Shift Data Analyst ... Gilbert Associates Incornorated .. Mr. P. Moyer, Startup and Test Engineer 2.

Preoperat!onal Test Results = 'Ihe inspector verified by review of the Official Field Copy of the w ce=pleted test procedure that the test results for the procedures listed below had been evaluated by the licensee and tHat he had deter-nined them to be acceptable and/or had taken proper corrective acti'en _; on all non-acceptable findings. These tests had Seen partially com - pleted and the test results partially accepted by tHe licensee, as-identified in previous RO inspections (Reports 50-289/74-25, Detail .. j[$ 2.a. & b.; 50/289/74-23, Detail 7.a; and 50-289/74-18, De tail 3.1T. (21), vith the exception of Etem c.

?K. 5 No deficiencies were identified during the inspector's review, and 55.5 the inspector's observations are included where apprepriate.

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TP 271/4 Main and Auxiliary Steam System Functional Test " i Test results were completed and accepted prior to power Q.

escalation testing. This included checking and resetting all g.. Main Steam Safety Valves.

(Report 50-289/74-08, Detail 2.d. (1)) _ However, during the Reactor Trip Test at 40% FP (TP 800/14), h,= one of these valves lif ted prematurely (about 4% below setpoint) ~" and then reseated. As a result, these valves were checked and = reset in the presence of the Code Inspector during this RO ' inspection and prior to escalation to the 76'; FP plateau. Test results were reported by the licensee to be acceptable; however, the results had not been reviewed by the TWG prior to ec=pletion of this RO inspection. The cause of the pre =ature lif t is under review by the licensee, and it has Been tentatively attributed to a procedural problem. This ites re=ains open pending final re- --- solution by the licensee and acceptance of the test results By the licensee.

b.

TP 600/11 Emergency Feed System and OTSG Level Control Test The outstanding test require =ents-CSections 9.4 and 7.6T.were.

completed and the test results-accepted prior to power escalation O testing (Report 50-239/74-08, Detai1 2.d(l)~) .. _ c.

TP 273/3 E=ergency Feedwater Turbine. and Motor-Driven Pumps- .... _... . Functional Test As a result of maintenanca, the requirements of this-test were.

repeated for each pump and the results of the retest were evaluated and accepted by the licensee prior to power escalation testing.

TP 600/13 Pressurizer Operation and Spray Flow Test . e TP 600/30 Hot Functional Test Checkpoints - f TP 360/1A Process Radiation Monitor Calibration and Functional Test-Portable At=ospheric 3.

Initial Startuo Test Program a.

Procedures y The inspector reviewed the following procedures and verified that .. previous RO:I coc:ments had been included in accordance with the .~' . licensee's con:mitments.

(Report 50-289/74-2.8, Detail 7.5' Items (6) and (7)) =X O 1449 253 _.-3 ... -. < .. ... ...... '~

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== -S-p, -= $ l b lJ, p (1) TP 800/11 Core Power Distri.bution (2) TP 800/14 Turbine / Reactor Trip Test 5i-i

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Additionally, the inspector reviewed appreved TCN's to procedures

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previously reviewed by the inspector. No deficiencies were iden-

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tified, and the inspector's review included the following: 25E =h (1) TP 800/21 Unit Startup and Pover Escalation - TCN's 1-5 (2) TP 800/18 Power Inhalance Detector Correlation Test-TCN's 1 and 2 (3) TP 800/11 Core Power Distribution-TCN's 2-5 b.

Test Results ' (1) Detailed Review of RO:I ~"'.: .. The inspector conducted a detailed review of the completed / partially completed procedures (Official Field Copy) listed below.

Additionally, the Partial Test Su= nary for these tests, as accepted by the licensee, was also reviewed and is listed below, where appropriate.

No deficiencies were identi-e fied, and the inspector's review included the following: Data sheets available and completed (at least 10% sampling '~ basis); raw data converted to test data; test exceptions and . deficiencies identified; corrective action performed; accep-tance criteria verified by licensee; test analysis reviewed by the appropriate persons; and inspector's verification that test results desonstrate the desired performance criteria and/or predicted results.

. _.. .. (a) TP 710/1 Zera Power Test Test is complete and the results were accepted by the licensee prior to power escalation testing.

. - (b) TP 800/2 Nuclear Instrumentation Calibration at Power Test is partially complete at.J included testing at the

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0-15%, 15% and 40% FP test plateaus. Additionally, a Partial Test Su= nary for the 15% and 40% TP test plateaus was approved by the licensee prior to power escalation g to the next higher test plateau.

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-~.g (c) TP 800/5 Reactivity Coefficients at Pcwer " Test is partially c:=clete end includ2d testing at +

the 40% FP test plateau. A.dd i t ienally, a Partial Test S m ry for the 40*: FP test 1449 251 . . ....... .. _.,_ ;; -

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plateau was approved by the licensee prior to power escalation to the next higher test plateau. The Power g.g Doppler coefficient was determined to be less negative g==l than design, i.e., -8.9 PCM/% power vice -13.7 PCM/% power.

K2 The licensee's a.nalysis indicated that extrapolation of Ur this value to 100% FP will meet the coefficient used in Q the Safety Analysis and that this value was consistent

== with results obtained at Oconne 2.

(d) TP 800/11 Core Power Distribution Test is partially co:plete and included testing at the 15% and 40% FP test plateau. Additionally, a Partial ~ Test Sum =ary for the 15% and 40% FP test plateaus was _ approved by the licensee prior to power escalation to M the next higher test plateau.

jq (e) TP 800/18 Power Imbalance Detector Correlation Test i a Test is partially complete and included testing at the 40% FP test plateau. Additionally, a Partial Test Su= mary G for the 40% FP test plateau was approved by the licensee prior to power escalation to the next higher test plateau.

. (f) TP 800/20 Rod Reactivity Worth Measurement Test is partially complete and included testing at the 40% FP test plateau. Additional 2 y, a Partial Test Su= mary for the 40% FP test plateau was approved by the licensee g prior to escalation to the next higher test plateau.

(g) TP 800/21 Unit Startup and Power Escalation Test Test is partially complete and included testing from 0 to 76% FP test plateau. Additionally, a Partial Test Su :maty.

for the 15% and 40% FP test plateaus was approved by the licensee prior to power escalation to the next higher test plateau. The inspector also observed the following: Licensee . evaluated the data obtained at the 0%, 15% and 40% FP test plateaus and authorized operation at the next higher power level; Licensee reset the high flux trips as .,= required by this procedure prior to power escalation to 11.. the next higher test plateau; and Licensee performed core 2.M and plant surveys to assure safe operation during the y increase of power level and arrival at the new power level.

y XX (h) TP 800/22 NSS Heat Ralance ". _ _ G Test is partially complete and included testing at the . 1449 255 ......... . -..... ,, T = ':Y.- :.. ::$::. . ?-l' - ..: ; - ~;;.::,

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= = =. . . a.- -:- -7-W . O -. g: 0-15%, 15%, 30%, 35%, 40%, 50%, 65%, and 76% FP test [. plateaus. Additionally a Partial Test Su==ary for the

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15% and 40% FP test plateaus was approved by the licensee 36)[ prior to power escalation to the next higher test plateau.

Mg]l i~El (i) TP 800/31 Pseudo Dropped Rod y{}h m=c Test is partially co=plete and included testing at the IK.

40% FP test plateau. Additicnally, the Partial Test (= Su==ary for the 40% FP test plateau was approved by-the licensee prior to power escalation to the next - higher test plateau.

.. (L.... (j) TP 800/32 Loss of Off-Site Power Test [f" e== Test is complete, and the results were accepted by } {22 5 the licensee prior to power escalation to the next =: - higher test plateau.

);j.;[ ..- 4 (2) Verification bv RO:I .-j - The inspector verified by review of the Official Field Copy '[?. G . of the completed test procedure or the partially completed

== test procedure with corresponding Partial Test Su==ary that ' - - - - the test results for the procedures listed below had been evaluated by the licensee and that he had determined them 5??~ to be acceptable and/or had taken proper corrective action on non-acceptable findings. No deficiencies were i'entified, - and the inspector's observations are included, were appropriate.

f~ ._ = :.;. (a) TP 800/8 ICS Tuning at Power = -)[ g ;---- Test is partially complete and included testing through - the 40% FP test plateau. Additionally, a Partial Test Sum =ary for the 15% and 40% FP test plateaus was approved = by the licensee prior to power escalation to the next it; higher test plateau.

(b) TP 800/14 Turbine / Reactor Trip hh; ._.

Test is partially complete and included the reactor trip at the 40% FP test plateau. Additionally, a Partial Test g.. ;_ Summary for the 407. FP test plateau was approved by the g[j; licensee prior to power escalation to the next' test plateau.

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.. - _ -8- ._ The turbine trip at 30% FP was rescheduled to be conducted during a planned shutdown from the 76% FP test plateau.

.=.2 However, during this RO inspection while operating at 76% jjp_ FP, an oil leak developed on the No. 3 turbine control g-valve which required re= oval of the turbine from service (5 to affect repairs. As a result, the turbine trip at 30% ppN was conducted. The licensee had not evaluated the accept-EE~ ability of these test results by the completion of the RO fi inspection. The inspector observed operations in the i.

Control Room during this occurrence and noted that plant paraneters were controlled within Technical Specification linits.

(c) TP 800/23 Unit Load Transient Test Test is partially complete and included testing at the 40% FP test plateau. Additionally, a Partial Test Su==ary - for the 40% FP test plateau was approved by the licensee

prior to power escalation to the next higher test plateau.

(d) TP 800/33 Psuedo Rod Ejection Test

Test is complete, and the results were accepted by the licensee prior to power escalation to the next higher test . plateau.

= - - (e) TP 800/36 Shutdown from Outside Control Room Test is complete, and the results were accepted by the _.

licensee prior to power escalation to the next higher test plateau.

(f) SP 710/2 Controlling Procedure for Post Fuel Lead Precritical Testing Test is complete, and the results were accepted by the licensee.

(Report 50-289/74-25, Detail 3.c) (3) Other Test Results The inspector observed during review of Tk'G Meeting Minutes for the period June 10-July 12,1974 (Meetings 116-122) and Official Field Copies of Partial Test Sumnaries for the 15%

== and 40% FP test plateaus that the results of the tests listed =+ below had been evaluated by the licensee prior to escalation gg. p to the next higher test plateau, pqy G = 1449 257 _ . e u

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(a) TP 800/6 Steam Bypass Testing . (b) TP 800/7 Feed Systes Operation and Testing =- 9 (c) TP 800/9 Turbine Generator Operation and Testing { (d) TP 800/12 Unit Load Steady State Test 5.x (e) TP 800/24 Incore Detector Testing F$C (f) TP 800/30 Power Escalation Checkpoints UE-T- 4.

Westinghouse DB-50 Reactor Trio Breakers k The licensee was provided a copy of Westinghouse Data Letter No. 74-2, dated February 19, 1974 which superseded instructions-in Westinghouse Bulletin No. NSD-TB-74-1, dated January 11, 1974. The earlier Bulletin

q had been discussed with the licensee during a previous RO inspection Ey--

(Report 50-289/74-05, Detail 13.5), and it was determined that the '7. Licensee's DB-50 breakers did not have nechanical undervoltage trip l:'.~. ?f devices.

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