IR 05000423/1985061

Insp Rept 50-423/85-61 on 850930-1101.No Violations Noted. Major Areas Inspected:Preoperational Test Program,Including Hot Functional Tests,Procedures & Test Results

ML20137E181
Person / Time
Site:	Millstone
Issue date:	12/31/1985
From:	Eselgroth P, Finkel A, Nicholas H, Vankessel H, Wink L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20137E149	List: IR 05000423/1985061 ML20137E145
References
50-423-85-61, NUDOCS 8601170191
Download: ML20137E181 (35)

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g U.S. NUCLEAR REGULATORY COMMISSION Region I Report N /85-61 Docket N License N CPPR-113 Priority Category B Licensee: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Power Station, Unit 3 Inspection At: Waterford, Connecticut Inspection Conducte_d: September 30 - October 4, October 7-11, October 15-18, tictober 21-24, October 28 - November 1

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Inspectors: MfVk 11- 31 -8$~

H. F. vanKbssel, Reactor Engineer date hf /s2-28-[6'

A. lE. 41nkel, Lead Reactor Engineer date k b-3[-Sf H. H. Nicholas, Startup Consultant date

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, nK J2-2f.- 8 r LU. Wink,ReactorEnineer date Approved By: /EY

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P. W. Esel h, Chief, Test Program Section, date Operati Branch, DRS Inspection Summary: Inspection on September 30 - October 4, October 7-11, October 15-18, October 21-24, October 28 - November 1 (Inspection Report No. 50-423/85-61)

A_reas Inspected: Routine, unannounced inspection of the preoperational test program (POT), including the witnessing of the Hot Functional Tests (3 INT-Appendices), the review of preoperational test procedures, the evaluation of

'the results of completed tests, emergency diesel generator status; review of

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8601170191 960109 PDR G ADOCK 0 %

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[ Inspection Summary (Continued)

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' startup test procedures; review of. inspections conducted by.NUSCO-QA and

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NNECO-QC/QA;_ independent measurements and licensee actions on previous

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inspection - findings'. .The inspection covered 454 hours0.00525 days <br />0.126 hours <br />7.506614e-4 weeks <br />1.72747e-4 months <br /> onsite by three NRC ~

region-based: inspectors and one startup consultant.

ill Results: No' violations were' identifie .

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'r-DETAILS 1.0 Persons Contacted North' east Nuclear Energy Company (NNECO)

A. Andreae, QC Supervisor R. Bradley, Startup Engineer M.~ Brown, I&C Supervisor J. Crockett, Superintendent Millstone 3 D. Dickerson, Startup Engineer A. Elms, Reactor Engineer

- Fringe, Startup Engineer

• E. Fries, Startup Engineer M. Gentry, Assistant Startup Supervisor B. Granados, HP Supervisor N. Hulme, Startup Engineer K. Jensen,_ Reactor Engineer

• J..Kelley, Station Service Superintendent

'W. A. Loweth,.Startup Engineer J. McConnell, Reactor Engineer D. McDaniel, Reactor Engineer

• D. Miller, Jr.', Startup Manager

'M. Potkin, Startup Engineer R. Sachatello, HP Supervisor S. Sudigala, Assistant Startup Supervisor Northeast Utilities Service Company (NUSCO)

B. Carlson, Project Engineer

• J. Chiloyan, Electrical Engineer D. Blumenthal,.NQA Engineer R. Bush,. Project Manager S. Fanhouser, Generation Engineer K. Gray, NQA Staff Assistant B. Kaufman, Project Engineer

• J. LaWare, Engineering Technologist, QA

• L. J. Nadeau, Project Engineer B. Nichols, Project. Engineer P. A. O'Connell, NCQA. Engineer

• J. Rhodes, Project Engineeer

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Stone and Webster Engineering Corporation (SWEC)

W. Matejek, Project Advisory Engineer

• F. Diliberto, Electrical Engineer j

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Westinghouse Electric Company

'C. Callaway,~ Startup Lead Engineer

• W. Potter, Operational Staff Engineer

'U.S.-' Nuclear Regulatory Commission T. Rebelowski, Senior Resident Inspector R.: J. Summers, Project Engineer

• Denotes those in attendance at exit meeting on October 31,_198 .0 Licensee's Actions on Previous Inspection Findings 12 . 1 Open Items on Preoperational Test Programs Sufficient information has been provided by the licensee ;o close the following Unre:cived Items:

-- (Closed), " Torque Switch Settings Motor Operated Valves" (423/85-27-03)

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(Closed), " Emergency Diesel Generator Fuel 011 Filter Internals Distortion" (423/85-05-06)

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(Closed), " Inadequate Operation of Solenoid Operated Reactor Head Vent Valves" (423/85-12-02)

The inspector has no further questions on these item .2 Follow-up on Other Open Items (0 pen) (Construction Deficiency Report 83-00-05 - Inadvertent uncoup-ling of pull-apart terminal blocks in Gould Motor Control Centers (MCC's)-

Uncoupling of pull-apart terminal blocks would result in loss of MCC function.for the safety-related equipment controlled by that MC ' Brackets have been designed to firmly secure the terminal blocks to prevent the male connector from pulling away from the female connecto Of the three (3) designs required for Millstone 3 systems, the single terminal block bracket is undersized and requires enlargemen The license 3 is changing the design drawings for the single terminal block bracket and will be making approximately 100 new unit This item remains open pending the following actions to be completed by the licensee:

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• Issue required engineering-drawings

• Verify installation of new brackets

• Verify that undersized brackets are not in stock (Closed) Unresolved Item 85-36-03 - Nuclear Engineering and Operations

. Procedure, NE0-6.01 assures the preparation and maintenance of a Material Equipment and Part List (MEPL) in compliance with 10 CFR 50, Appendix B, Criteria II, Regulatory Guide 1.143 and Procedure NEO-2.1 The licensee's Procedure NE0-6.01 dated November 1, 1984, defines the purpose, applicable documents and the references required to establish a Material, EquipiTient and Parts List for the Millstone 3 sit In support of NE0-6.01, the following documents have been issued:

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Specification PUI-QA-2.02, MP3 Category 1 Systems, Components and Parts, dated October 29, 1985. This procedure defines the documents to be used as the Millstone 3 MEPL prior to the gener-ation of the final MEPL document and provides for the transition of this document taken to the final Millstone 3 MEPL in the Production Management Maintenance System (PMMS) data bas Administrative Control Procedure ACP-QA-2.13A, Revision 0, defines the procedure for the implementation of computer. software. New programs, as well as software changes to existing programs,.will be controlled within the licensee's formal documentation control

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syste Material, Equipment, and Parts List (MEPL) were issued October 11, 198 This controlled computer listing identifies safety related components that are not listed in the PMMS progra The type of components listed in the MEPL are listed below:

• Structures

• Piping

• Small Bore Pipe Hangers

• Large Bore Pipe Hangers

• Cables

• Raceways The issuance of the MEPL program documentation and the program verif-ication task closes this unresolved ite .0 preoperational Test (POT) Program 3.1 Test Witnessing Scope Selected steps of the Hot Functional Test Procedures (appendices),

as listed in Attachment A, were witnessed by the inspecto n:

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A Test witnessing by the inspector included observations of:

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• 'Overall crew ~ performanc *

Use of latest revised and approved procedure by test personne *

Designation of one person in charge of conducting the test *

Availability of sufficient test personnel to perform the test * Coverage of. test prerequisite * .Use of acceptance' criteria to evaluate test result *

Verification that plant supporting systems are in servic *

In-service status of calibrated special test equipment required-by the test procedur *

Timely and correct action by test personnel during the performance of the test *

Data collection for final analysis by test personne The inspector independently verified readings of system parameters

.during the test Discussion

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3 INT-3002, "RCP Data" Vibration readings were taken independently by the inspector on four Reactor Coolant Pumps for both the frame and the shaf The highest shaft vibration reading (13 mils) was for the B pum This reading was within the allowable value of 15 mils. All of the readings with the hand held vibrometer were compared with the readings on the main control panel. Good agreement was evident between these two sets of readings. The hand held vibrometer had a valid calibration sticker (due for recalibration on 12-13-85).

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3 INT-3008, "RTD Cross Calibration" Four RTDs, out of a total of 24, were not installed yet. The thermocouple map appeared acceptable. Westinghouse will extra-polate the data to calculate what the 4 missing RTDs should have read.

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3 INT-3019, " Auxiliary Feedwater (AFW) System" Apart from witnessing the procedural steps for the flow data of the motor driven pumps, the inspector witnessed the checkout of the turbine speed controls for the turbine which drives tre AFW Pump-P-2. The inspector took data independently to verify rpm, flow rates, pump pressures on suction and discharge. A Heise gauge (QA-5075) was available for the pump discharge pressure measurement It was due for recalibration on November 2, 198 The following data were obtained (on October 9, 1985):

Pump Suction Pump Discharge Speed T:me Pressure psig Pressure psig rpm 9:00 am 1 (2)

9:40 am 1 (1)

10:20 am 1 (1)

(1) With hand-held tachometer (2) With local panel indicator The following observations were made during the test:

(1) No test procedure was used by the NNECO test engineer for what basically was a Phase 1 test. Such a procedure was available but was not use (2) Test Change 9 of 3 INT-3019 eliminated step 41 on the grounds that the test was completed sufficiently to perform the phase 3 ste (3) Data on the p' ump and the turbine governor adjustments were not recorded on an official documen (4) The manufacturer's representative (Terry) did an excellent job in adjusting the Woodward Governor. Control linkages had to be remachined initiall Final adjustments left the turbine operation within the name plate data and specifica-tion (5) The hand-held tachometer, used to check the shaft rpm, was a Yogokawa Electric Works (YEW) tachometer with photoelectric probe, Model 363 '(6) A turbine trip initiated from operation at 4100 rpm at the local control panel did not fully stop the turbine (stayed at 1400 rpm). The stop valve had to be closed manually to stop i This problem will be resolved after the endurance run.

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3 INT-3027, " Primary Reliefs" All valves-(3) were reset on October 7, at r,3 t of the POT program, under the guidance of the manufacturer's repre;cntative (Crosby).

The inspector witnessed the resetting of valves B and C. Two Heise gauges (QA 5035 and 5046) were used to measure both air pressure and total pressure (air + RCS). Both gauges had valid calibration stickers. All valves had.to be adjusted approximately 100 psi upward to obtain the desired set pressure of 2500 psi On October 9, all valves were found to be leaking and two of the valves had to be gagged to reduce leakage. Discussions with the licensee on October 9 revealed that they had a recovery plan as follows:

(1) Obtain parts to repair the 3 existing valve (2) Modify 3 new valves (from Marble Hill) to Millstone 3 plant

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specifications at Crosb (3) Obtain history of factory testing for existing valves (hot test versus cold test).

(4) Hot test (pending decision) all valves after repair or modification in the Crosby facilitie (5) In the meantime, try to get the valves to reseat by plant maneuvering INT-3011, " Pressurizer Testing" Witnessed steps 7.3.1.9.2 to 7.3.2.4 and observed the following:

(1) Some identification numbers of annunciators in use, during the test, have no labels on the main control panel (panel 4F1-14 through 4-14). Drawings in the control room show that titles presently do exist but there are no "UNSAT" stickers on the pane (2) The procedure indicated annunciators in panel 2D of the main control board (Section 2) but panel 2D was misread as 2 (3) None of the main control board panels have identification labels. This added to the confusion of 1 and 2 above as experienced during this tes I

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3 INT-3005, " Ventilation System Tests" Independent measurements were taken by the inspector for four critical environmental zones as folicws:

• CS-01 and 02 for Containment Building

MS-01 for MSV-Building

• ES-01 for ESF Building Temperatures in excess of the normal zone temperatures were measured in all of the 4 zones. These measurements were taken in parallel with those measured by the licensee for the 3 INT-005 test The licensee readily acknowledged these environmental problems and will deal with them by adding more insulation to piping or, where indicated, redesign the HVAC system to either add cooling capacity or to better utilize available cooling. If these activities are not successful, environmental qualification of safety related equipment will be reassessed. Peak temperatures measured in the 4 environmental zones mentioned above were:

• ES-01: 127 F, valve room ESF with door closed and no temporary fa F, valve room ESr with door open and no temporary fa F, valve room ESF with door open and temporary fan with elephant trunk * MS-01: 132 F in area near MSIVs at elevation 75 ft (October 10,1985).

114F on contact with 9CC9870F1, an electrical connector near MSIV at elevation 75 ft. (October 17,1985).

• CS-01/02: 100.9F at elevation 24 ft near 3FWA FT51A2, with equipment hatch ope .6F at elevation 48 ft near 3POPACB1121, with equipment hatch ope For all of the measurements above, a calibrated thermometer (Precision Platinum Thermometer, Barnes, Model 33-100, NRC N ) was used by the inspecto ~

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3 INT-3027, " Pressurizer Reliefs" Witnessed the preparations for steps 7.3 to 7, Problems have been experienced with both PORVs, PCV-455, and 45 PCV-455 would not open. The block valve had to be opened first to put pressure under the PORV seat prior to opening it to establish discharge to the Pressurizer Relief Tank (PRT). The other valve, PCV456, had limit switch problems. Both problems had to be resolved before the test could continu It was noticed that the scale of RCS-TI468, for the PRT, had scale divisions of fractions of a degree ( F); scale progression was 50, 112.5, 175 F. It is extremely difficult to read such a

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scale quickly. This item was discussed with the license It was discovered that this item was identified for correction under a given work order but had later been deleted inadvertentl The licensee.was planning to correct this omissio INT-3037, "RCS Heat Loss Test and 3 INT-3030, "RCS-Leak l Detection" These tests were done in tandem and, consequently, the witnessing was done in tandem as well. Plant computer software programs existed but had not been checked out against manual observation One of the objectives of these tests was to troubleshoot these software programs. The RCS operation had to be stabilized within narrow bands for the significant parameters. The heat loss test (3037) is more limiting in this respect. Valid data were collected for the heat loss test but the leak test had to be aborted later because of inadvertent operation of the Volume Control Tank which caused an unknown loss of water from the syste The RCS leakage test (3030) was repeated successfully on October 28. Acceptable'results were obtained with the hand calculation Identified leakage was well within the required 10 gpm ma Unidentified leakage was below the 1 gpm max. The computer printout, however, did not match the hand calculations. The licensee is working on resolution of the computer proble ~~

3 INT 3031, " Voice Page/ Evacuation Alarm Test" Witnessed steps 7.2 and 7.3 of this test in containment. The following observations were made:

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(1) The test ' instrument, a sound meter, was not identified in the procedur .(2) There was nc calibration sticker on the sound meter. The test. supervisor stated that it was calibrated at the factory and that it has a device to test sensitivity. This test was done prior to a'ny use for 3 INT-303 (3)' Background noise was extremely high with the highest level of 110 dB near the RCP motors and the lowest level of 93 dB near.the Regenerative Heat Exchange (4) The test was conducted at all 6 levels and was determined to be "Unsat" for both voice and alarm at all location Findings

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Re: 3 INT-3019, "AFW System": The phase 1 portion of the test was conducted without the benefit of a preoperational test pro-cedure. Valid baseline maintenance data may be lost as a resul This item will be Unresolved Item 423/85-61-0 .Re: 3 INT-3005, " Ventilation System Tests": Temperatures in ex-cess of the normal environmental zone temperatures were found in four critical zones i .e. , CS-01, 02; MS-01, and ES-0 Sever-al actions were initiated by the licensee to bring these tempera-tures down to acceptable levels, including the addition of insu-lation for piping and valves, the addition of temporary ventila-tion and adjustment of air distribution. The inspector will follow this Unresolved Item 423/85-61-02 in future inspection Re: 3 INT-3011, ' Pressurizer Testing": Some (annunciator) panel problems were identified during this test. These problems appear Human Factors related. The inspector will follow up under Unresolved Item 423/85-61-0 Re: 3 INT-3027, " Pressurizer Reliefs": As discussed above, both the PORVs (with block valves) and the Pressurizer Relief Valves ;

(PRVs) experienced problems during the performance of this tes Plans are to replace the PRVs with new valves which have been hot tested at the manufacturer's facilities. The problem of the block valves for the PORVs and the PORVs themselves (experienced leakage of steam) will be addressed by the licensc: after com-pletion of the Pre-Core-Hot Functional Test. The inspector will follow this Unresolved Item 85-61-04 in future inspection L ,

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3.2 Test Procedure Review

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Scope L

The test-procedures listed in Attachment B were reviewed for admin-1strative and, selectively, for technical adequacy and to verify that

. test planning satisfies regulatory guidance and licensee commitment Discussion The first PORC/JTG approved preoperational test procedures (Revision 0), in many instances, continue to be issued late for NRC revie Approved test. procedures are to be submitted to the NRC 60 days prior to start of the test. Although many of those Rev. O procedures were reviewed by the NRC'in draft form, their review has to be finalized before the test is performe The_ inspector concentrated on the review of the approved procedures (Rev. 0) which were issued since the last inspection period (50-423/85-51).

'.The procedures were examined'for:

• Management review and approval

• Proc < Jure format

• Clarity of stated objectives

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• ~ Pre-requisites

• Environmental Conditions

• Acceptance criteria and their sources

• References

• Initial conditions-

• Attainment of test objectives

• . Test performance documentation and verification

• Degree of detail for test instructions

• Restoration of system to normal after testing

• Identification of test personnel

• Evaluation of test data

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=* - Independent verification _of-critical steps or parameters

• Quality' control.and assurance. involvement

.With reference to inspection report 50-423/85-51, it had been noted in Section 3.5 that the original preoperational test (P0T) procedures 1T3406-P and T3409-P had been deleted and would be replaced by sur-

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veillance type procedures:

• ' Station Procedure SP-3446F31, " Refueling SSPS Tests", Rev. O.

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• Station Procedure SP-3446B11, " Solid. State Protection System

- (SSPS) Operational Test", Rev. This deviation from.preoperational test commitments'was discussed with the license It was again_ stressed by the licensee that these

' procedures would be superior to the deleted POT procedures in.that all the. elements of the instrument channels _from sensors to the trip coils would be given a functional check. This, the licensee _said, is far in excess of-the checks provided by the deleted POT-procedure ,

The surveillance procedures had not been completed and approved by PORC until October.30,.1985. The unapproved procedures were reviewed

. by the inspector. This review confirmed what the licensee claimed above with regard to the adequacy of the surveillance procedures to-

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be -substituted for POT .

It was noted by the inspector,,in a previous inspection, that the surveillance procedures would not be' approved by the Joint Test Group (JTG) as is the requirement.for POT procedures. The licensee indicated

~JTG coverage of these procedures would be provide Findings The final review of the surveillance procedures for the Reactor

. Protection System (RPS) or SSPS, and the use of these procedures as POT procedures will be addressed in the next POT inspection under Unresolved Item 85-61-0 ,

3.3 Test Result Evaluation

. Scope I The test procedures listed in Attachment C were reviewed to verify that adequate testing was accomplished in order to satisfy regulatory guidance and licensee commitments and to ascertain whether uniform  !

criteria were being applied for evaluating completed preoperational tests in order to assure their technical and administrative adequac .-

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' Discussion The test results were reviewed for:

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• Test changes

= . Test exceptions

• Test deficiencies

• Acceptance criteria

• . Performance verification

• Recording of conduct of test

• - QC inspection records

• System restoration to normal

• - Independent verification of critical steps or parameters

• Identification of test personnel

• ' Verification that the rest results have been approved In the course of the review, it was noted that a substantial number of test exceptions,.UNSATS and test changes had been identified by the licensee for future actio It was pointed out to the licensee that the documents for the processing of UNSATS and test deficiencies would have to be pulled together into a common file for each test to avoid missing the deadline for the review of these documents by the NRC. -The licensee responded by organizing a separate system, the

" Orange Folder System", to accomplish this objectiv In a subsequent meeting with the licensee in the Regional NRC Office,

.the identified UNSATS and Test Changes were linked to the various startup milestones for completion or resolution. The inspector iden-tified 42 items in the licensee's open items listing (linked to Fuel Load) which were considered "significant to safety". The. licensee is planning to give thest 42 items priority in their processing of the entire listin .

Findings No discrepancies or unacceptable conditions were noted in the review of these procedures with the exception of the following items:

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15 Procedure N Title "UNSAT" Item (Licensee's No.)

'T3314-GP -Intake Structure Ventilation 4653; 4735

.T3313-LP Containment Purge 5143 T3321-DA Feed Pump Drive Lube Oil 4697 T3323-DA Gland Seal and Exhaust 4571 T3323-BA002 Turbine Lube Oil 2995; 3086 T3347-CA Main Transformer / Iso. Bus 5207

T3402-A- RCP Vibration Monitoring 3981 T3314-HP Emerg. Gen. Enclosure HVAC 5025, 5156, 5185 T3344-AP018 Load Center 32T 883 T3344-BA050 MCC-31-1K (3B1) 3186 T3344-BA045 MCC-32-4H (184) 1373 T3330-DP Charging Pump Cooling 4855 73324-BA Main Generator Seal Oil 3272; 3273 T3333-A Nitrogen 1982-T3340-BA Water Treating 470 3 INT-2001, 3J8 Hourly Datalog 4171

~3 INT-2001,.3J10 Sequence of Events 5800 3 INT-2001, A3A2 Reactor & SAR Monitoring 4200 3 INT-2001, A3J7 Pre / Post Trip Re INT-2001, A3R4 Reactivity Parameters 2688

'3 INT-003 ESF w/o Loss of Power 5324; 5328; 5329; 5331 5332; 5333; 5334; 5335 5336; 5344; 5394; 5396 5397; 5398; 5399; 5405 5422; 5423; 5425; 5426 T3347-BA001' RSST-A 5074; 5107 T3347-BA002 RSST-B 5107; 5992 T3339-BP BP-Chemical Feed 5214; 5280 T3301-P001 RC System 3783; 3782; 3834; 4014 The above exceptions will be reviewed by the inspector on a subsequent inspection for their resolution and approval by the licensee under Unresolved Item 423/85-61-0 The progress on the 42 items in the licensee's open item list (for Fuel Load) will be followed under Unresolved Item 423/85-61-0 .4 Emergency Diesel Generator '(EDG) Status Scope

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Inspect the installation, flushing, and testing of the modified lube oil system (duplex strainers) of the Emergency Diesel Generators (EDGs).

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Witness and review the test results for the acceptance tests (35 consecutive starts and stops) of the EDGs A and ___

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Discussion

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Witnessed installation work on the modified lube oil systems for EDG A and B. The new strainer and the old twin units are presently-installed off the skid. Supply and return lube oil piping is crossing the pathway near the diesel. Work was progressing satisfactoril Preparations for flushing of the lube oil piping were being made on October 28, 198 The test with the 35 consecutive starts and stops was done successfully for Unit "A" from October 19 to 22, 1985. The inspector witnessed a number of starts and stops spread out over the 3 days of testin Findings No noncompliances were identified by the inspector within the scope of this inspectio .0 Startup Test Procedure Review 4.1 References .

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• - Regulatory Guide 1.68, Revision 2, August 1978, Initial Test Programs for Water-Cooled Nuclear Power Plants

• Millstone Unit 3 FSAR, Chapter 14, " Initial Test Program"

• Millstone Unit 3 Technical Specifications, Proof and Review Copy

• Millstone Unit 3 Safety Evaluation Report, Chapter 14, " Initial Test Program"

• Westinghouse - Millstone Unit 3 NSSS Startup Manual, Revision 1

• Westinghouse Nuclear Design Report, WCAP-10791, February 1985 4.2 ' Procedure Review Scope 4. During the startup test phase of reactor operations, a sampling of the licensee's test procedures are to be reviewed for their conformance to the requirements and guidelines of the above references, Test procedures will be reviewed for the following attributes:

• Appropriate management review and approval has been accomplishe * Appropriate committee review has been accomplished.

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• Procedure is in the proper forma * Test objectives are clearly stated and consistent with the FSA * Appropriate references are liste *

Appropriate prerequisites and precautions have been include * Initial test conditions are specifie * Acceptance criteria are clearly state *

Provisions have been made to identify test equipment ,

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Provisions have been made to identify personnel per-forming the tes *

The procedure is technically adequate and workabl = Temporary jumpers, installations and lifted leads are properly restore *

Provisions have been made for recording, evaluating and approving test dat * Provisions have been made to identify test deficiencies and exceptions and to document their resolution .2.2 During this inspection, the following procedures were reviewed:

• 3-INT-4000, Initial Fuel Load

• 3-INT-4000, Appendix 4001, Nuclear Instrumentation Systems a 3-INT-4000, Apper. dix 4002, Operational Alignment -

Nuclear Instrumentation System

• 3-INT-4000, Appendix 4003, Core Load Instruments and Neutron Source Requirements

• 3-INT-4000, Appendix 4004, Inverse Count Rate Ratio Monitoring

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3-INT-4000, Appendix 4005, Initial Core Loading ,

• 3-INT-4000, Appendix 4006, Core Map All procedures were preliminary copies since none of these procedures have been issue .3 Discussion During the review of the procedures. identified in paragraph 4.2.2 for

'the attributes listed in paragraph 4.2.1 several apparent defects were identified. They included not fully conforming to the commitments of Chapter 14 of the FSAR, not including necessary and appropriate precautions and an incomplete reference list. In addition, a complete review was not possible since the draft procedures were missing pre-requisite checklists on valve alignments and snubber A meeting was held with the Millstone 3 Reactor Engineer to discuss the inspector's concerns. As a result of this meeting, the Reactor Engineer agreed to: Review Chapter 14 of the FSAR and incorporate commitments into the procedures including: briefing of all test personnel prior to the test, requiring suspension of fuel loading if an unexpected change in reactor coolant system water temperature occur . Review the Technical Specifications and insure that: all re-quired limiting conditions for operation are identified and established, all conditions requiring halting of core alterations are identified, and procedural checklists to track periodic refuel surveillances are ccmplet . Include cautions within the procedures to insure that test per-sonnel are aware of the potential radiation hazard associated with movement of a fuel assembly containing a primary sourc .- Expand the reference list to include all plant procedures used during the performance of the test procedur !

-The inspector will review.the approved procedures during a subsequent routine inspection to insure that these commitments have been incor-porate .4 Findings Within the scope of this inspection, no violations were identifie _ - . - --.

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-5.0 QA/QC Interface Scope 1 NVSCO QA and _NNEC0 QA/QC surveillances were reviewed for coverage of the Hot Functional Tes Discussion

' Several NUSCO'and NNECO surveillance reports as identified in Attachment D were reviewed by the inspector for scope of inspection and the nature of their findings. All of these reports are related to the Hot Functional Tests. Good covera 99 was provided for these test Findings No noncompliances were identified by the inspector within the scope of the revie .0 Independent Measurements The inspector performed independert measurements of critical area temperatures, reactor coolant.pur vibration readings, and auxiliary

~feedwater pump performance as described in Section ,.

7.0 Exit Interview At the conclusion of the site inspection, on October 31, 1985, an exit interview was conducted with the licensee's senior site representatives (denoted in Section 1). The findings were identified and previous inspection items were discusse '

At no time during this inspection was written material provided to the licensee by the inspector. Based on the NRC Region I review of this report and discussions held with licensee representatives during this inspection, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction s.

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Attachment A Test Witnessing Procedure No. Title Re Approval Date

3 INT-3000 Precore Hot Functional Test 0 9/3/85 3 INT-3002 Reactor Coolant Pump Data 0 9/25/85-3 INT-3003 RHR Systems Operation 0 8/20/85 3 INT-3004 Solid Plant Pressure Control 0 8/13/85

- 3 INT-3005 Ventilation System Tests 0 2/11/85 31NT-3006 Steam Generator Blowdown Test 0 10/10/85 and Flow Calibration 3 INT-3007 Thermal Expansion and Restraint 0 6/25/85 Test 3 INT-3008 RTO Cross Calibration 0 8/15/85 31NT-3009 Component Cooling Water 0 10/3/85 3 INT-3010 Main Feedwater System 0 8/23/85 3 INT-3011 Pressurizer Testing 0 10/2/85 3 INT-3012 Rod Control System 0 9/24/85 3 INT-3013 Steam Generator Chemical Feed 0 8/12/85 3 INT-3014 Auxiliary Shutdown Panel 0 9/8/85

.3 INT-3015 Service Water System 0 9/26/85 3 INT-3016 Chem. Vol. Control System 0 9/21/85 3 INT-3017 RC Loop Isolation Valves 0 6/3/85 31NT-3019 Auxiliary Feedwater 0 9/30/85 31NT-3020 Main Steam 0 10/1/85 3 INT-3021 Pipe and Pipe Support Transient 0 7/18/85 Vibration Testing

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Procedure N Title Re Approval Date 3 INT-3022 Snubber Expansion Examinations 0 9/20/85 3 INT-3023 ' Turbine Generator 0 10/1/85 13 INT-3024 Electrical Distribution 0 9/17/85 3 INT-3025 Steam Dump and Controls 0 8/21/85 3 INT-3026- Loose Parts Monitoring System 0 9/30/85 3 INT-3027 Primary Reitef Valve Testing 0 9/21/85 3 INT-3029 Chemistry Guidelines 0 4/10/85 3 INT-3030 RCS Leak Detection 0 10/2/85 3 INT-3031 Voice Page/ Evacuation Alarm 0 9/26/85 Test 3 INT-3032 Boron Thermal Generation System 0 8/14/85 31NT-3033 Post Accident Sampling System 0 10/21/85 3 INT-3035 Loss of Instrument Air 0 10/10/85 3 INT-3036 Feedwater Hammer 0 10/8/85 3 INT-3037 RCS Heat Loss 0 9/10/85

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Attachment B Test Procedure Review and Verification PORC/JTG Procedure N Title Rev. Approval Date-3-INT-2001 ' Computer Programs Test, Appendix 3PB 0 9/13/85-3-INT-2001 Computer Programs _ Test, Appendix 3P5 0 7/16/85 Secondary Plant Performance T3314-1P ' Supplemental Leak Collection and Release 0 9/10/85 System T3316-CP Steam Generator Blowdown System 0 8/19/85 T3319-BP Condensate Makeup and Drawoff System 0 8/9/85 T3319-CP001 Condensate Polishing System 0 10/7/85 T3319-CP002 Condensate Liquid _ Waste System 0 9/18/85 T3322-P Auxiliary Feedwater System 0 9/6/85 T3325-DA Condensate Tube Cleaning System 0 9/17/85

.T3331-DA- Hot Water Heating and Preheating 0 8/14/85 T3335-BP Radioactive Liquid Waste 0 10/11/85 T3335-CP Boron Recovery System and Reactor Plant 0 9/20/85 Drains-T3358-P Radioactive Solid Waste System 0 8/15/85 T3347-BA001 Normal Station Service'XFMR 15G-3SA 0 8/5/85-T3347-BA002 Normal Station Service XFMR 15G-3SB 0 9/6/85 T3347-CA Main Generator Step-up Transformer 0 7/18/85 15G-3X A/B T3349-P001 Appendix D01 Application Programs 1 8/17/85 T3349-P001 Appendix E01 Safety Parameter Display 1 8/17/85 System

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' Attachment B -2 PORC/JTG Procedu're' No. Title- Rev. Approval Date

.T3349-P00 Safety Parameter Display System Timing 0 9/20/85-T3720-BP- Station Emergency Lighting 0 9/21/85 3-INT-2001 Computer Programs Test Appendix 3J5 0 10/19/85 Setpoint Supervision

- 3-INT-3000 ~ Hot Functional Test Appendix 3033 Post 0 10/21/85 Accident Sampling System T3341-CP CO2 Fire Protection System 0 9/4/85

- T3312-CP Containment Atmosphere Monitoring System 0 8/27/85 3-INT-3000 Hot. Functional Test Appendix 3001 0 9/10/85 Reactor Plant and Turbine Plant Sampling-3-INT-3000- Hot Functional Test Appendix 3008 RTD Cross 0 8/15/85 Calibration 13-INT-3000 Hot Functional Test Appendix 3009 Component 0 10/3/85 Cooling Water 3-INT-3000 Hot Functional Test Appendix 3012 Rad 0 9/24/85 Control System 3-INT-3000 Hot Functional Test Appendix 3013 Steam 0 8/12/85 Generator Chemical Feed 3-INT-3000 . Hot Functional Test Appendix 3015 Service 0 9/26/85 Water Systems

' 3-INT-3000 Hot Functional Test Appendix 3020 Main Steam 0 10/1/85 3-INT-3000 Hot Functional Test Appendix 3024 Electrical 0 9/17/85 Distribution-3-INT-3000 Hot Functional Test Appendix 3031 Voice 0 9/26/85 Page/ Evacuation Alarm 3-INT-3000 Hot Functional Test Appendix 3035 0 10/10/85 l'

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Procedure No.' -Title

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PORC/JTG Rev.: Approval Date SP3446-B11 Solid State Reactor Protection System .0 10/30/85-

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M 'SP3446-F31  ; Refueling SS RPS Tests 0 10/30/85

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3-INT-3013 Steam Generator Chem. Feed 0 8/12/85

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.'33-INT-3020 Main Steam 0 10/1/85

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3-INT-3024- Electrical Distribution -0 9/17/85

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' Voice Page/ Evacuation Alarm Test 0 9/26/85 Hl3-INT-3031

? 3-INT-3035 Loss of Instrument Air 0- 10/10/85

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Attachment C Test Results Evaluation

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PORC/JTG Procedure No. : Title Rev. Approval Date J3304-AP002' Charging Pump Flow Balance 0 1/8/85 Test Results - 9/10/85 T3308-P001 High Pressure Safety Injection Flow Balance 0 1/26/85 Test Results' 8/20/85

.T3312-B Containment Leakage Monitor 0 2/15/85-Test Results 9/20/85

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.T3313-BP Containment-Air Recirculation System 0 2/11/85

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Test-Results 9/10/85

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-T3313-CP CRDM Air Cooling System 0 9/12/84 Test Results- 9/10/85 T3313-EP Containment Purge Air System 0 12/21/84

' Test Results 9/16/85-T3314-GP Intake Structure. Ventilation 0 12/22/83 Test Results 9/6/85 T3315-AA -Turbine Building Ventilation 0 5/16/84 TestiResults 3/15/85 LT3315-DA_ Technical Support Center Ventilation 0 3/25/85 Test-Results 9/12/85 T3315-EA /,uxiliary Boiler. Room Ventilation 0 3/5/84 '

Test Results 10/25/85 T3319-AP Condensate-Systea 0 6/15/85 Test Results 9/30/85 1T3316-AP002 Main Steam Generator Secondary Hydrostatic 0 11/20/84-

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Test'Results 8/9/85 T3321-DA Turbine Feed Pump Drive Lube Oil Supply and 0 9/19/84 Trip Test Results 8/14/85

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PORC/JTG -

. Procedure No. LTitle~ .Rev. Approval Date

~T3323-BA001 Lube 011 Purification 0 3/7/84 Test Results 8/25/84 iT3323-BA002 Turbine Lube Oil System 0 7/25/84 Test Results 9/17/85 JT3323-DA . Gland Seal Steam. System 0 2/27/85 Test-Results- 9/12/85 T3324-EA Generator Alterrex Excitation 0 11/7/84 Test 'asults 9/24/85

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T3330-DP- . Charging Pumps Cooling System 0 1/29/85 Test Results 9/16/85 T3332-AP001 Instrument Air - Turbine Build'ing 0 2/24/84 Test Results 10/5/84

~T3332-BP -Containment Instrument Air System 0 7/2/84 Test Results 8/26/85-T3324-BA ' Main Generator Seal Oil 0 4/2/84-Test Results 7/16/85

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-T3333-A Nitroge /8/84 Test Results 6/27/85 T3345-BP003 Channel 3: 120 VAC Vital 0 3/5/84

,- Test Results 3/27/85 T3345-BP-004 Channel 4: 120 VAC' Vital 0 3/5/84 Test Results 3/27/85 1T3345-BP005 Channel 5: 120 VAC Non-Vital 0 5/23/84 Test Results 3/27/85 T3345-BP00 Channel 1: 120 VAC vital 0 3/5/84 Test Results 3/27/85 T3345-BP002- LChannel 2: 120 VAC Vital 0 3/5/84 Test Result /27/85 T3340-AA -Domestic Water System 0 10/6/83 Test Results 8/15/84 i-

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PORC/JTG iProcedure-No." Title' Rev. Approval Date

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.T3340-BA Water Treating System 0 5/4/83 : Test Results 6/21/84 T3342- 001 6900V Switchgear. Bus 35A 0 6/19/84 Test Results 1/31/85 T3342-A002 -6900V Switchgear Bus 35B 0 6/19/84 Test Results 1/31/85-

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T3342-A003 6900V Switchgear Bus 35C~ 0 6/19/84 Test Results 1/31/85

.T3342-A004- 6900V~Switchgear Bus 350 0 6/19/84 '

Test Results 1/31/85

'T3342-P001

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4160V Switchgear Bus'34A 0 11/16/83 Test Results 1/30/84 T3343-P002' -4160V Switchgear Bus 348 0 11/17/83

. Test Results 1/30/84 ST3343-P003 4160V Switchgear Bus 34C 0 11/17/83 Test Results 1/30/84 T3343-P004 4160V Switchgear Bus 34D 0 11/17/83

!. Test Results 1/30/84 T3344-AP02 V Load Center 32 /9/83 Test Results 10/5/84 T3344-AP022 480V Load Center 32X 0 8/9/83 Test Results 9/20/84

.T3344-AP021 480V Load Center 32W 0 8/9/83 Test Results 4/6/84 T3344-AP020 480V Load Center 32V 0 8/9/83 Test Results 10/24/84 T3344-AP019 480V Load Center 32U 0 8/9/83 Test Results 4/6/84 T3344-AP018 480V Load Center 32T 0 8/9/83 Test Results 3/20/84

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Attachment C 4 PORC/JTG

~ Procedure N Title Rev. Approval Date T3344-AP017 '480V Load Center 32S 0 8/9/83 Test Results 10/24/84 T3344-AP016 480V Load Center 32R 0 6/24/83 Test Results 3/20/84 T3344-AA015 480V Load Center 320 0 8/9/83 Test Results 3/28/84 T3344-AA014 480V Load Center 32P 0 8/9/83 Test Results 3/1/84 T3344-AA013 480V Load Center 32N 0 8/9/83 Test Results 10/25/84 T3344-AA012 480V Load Center 32M 0 8/9/83 Test Results 3/20/84 T3344-AA011 480V Load Center 32L 0 8/9/83 Test Results 3/1/84 T3344-AA010 480V Load Center 32K 0 8/9/83 Test Results 3/1/84 T3344-AA009 480V Load Center 32J 0 8/9/84 Test Results 3/1/84 T3344-AA008 480V Load Center 32H 0 8/9/83 Test Results 3/1/84 T3344-AA007 480V Load Center 32G 0 8/9/83 Test Results 3/1/84 T3344-AA006 480V Load Center 32F 0 8/9/83 Test Results 3/1/84 T3344-AA005 480V Load Center 32E O 8/9/83 Test Results 3/1/84 T3344-AA004 480V Load Center 320 0 8/9/83 Test Results 3/20/84 T3344-AA003 480V. Load Center 32C 0 8/9/83 Test Results 3/20/84

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PORC/JTG

.: Procedure N Title- Rev. Approval Date T3344-AA00 V Load Center 328 0 8/9/83 Test Results 10/25/84

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-T3344-AA001- 480V Load Center 32A 0 8/9/83

' Test Results ~ 3/1/84 T3'344-BA001 (480V MCC Bus 32-1G- 0 8/26/83

- Test Results 7/25/84 T3344-BA002 480V MCC Bus 32-2G 0 8/26/83

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Test Results 6/14/84 T3344-BA003 480V MCC Bus 32-3G 0 8/26/83 '

.. Test Results 6/14/84 LT3344-BA004 480V MCC Bus 32-5G 0 8/26/83 Test.Results 7/25/84 T3344-BA005' -480V MCC Bus 32-1H 0 8/26/83 Test Results

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7/25/84

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T3344-BA006 480V MCC Bus 32-2H 0 8/26/83 Test Results 6/14/84 T3344-BA007- 480V MCC bus 32-3H 0 8/26/83 Test Results" 6/14/84

T3344-BA008 480V MCC Bus 32-5H 0 8/26/83 Test Results 7/25/84 T3344-BA009 480V MCC Bus 32-1F .0 8/26/83 Test Results 2/25/84 T3344-BA010 480V MCC Bus 32-2F- 0 8/26/83 Test Results- 9/5/84

"T3344-BA011 480V MCC' Bus 32-4F 0 8/26/83 Test Results 3/1/84 T3344-BA012 480V MCC bus 32-1J 0 8/26/83 Test Results 3/1/84 T3344-BA013 '480V MCC Bus 32-2J 0 8/26/83 Test Results 7/25/84 x

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PORC/JTG Procedure No. Title- Rev. Approval Date LT3344-BA014' .480V MCC' Bus 32-4J- 0 8/26/83 Test Results 3/1/84

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T3344-BA015 480V MCC Bus 32-3E - 0 8/26/83

. Test Results 7/25/84 T3344-BA016 480V MCC Bus 32-10- 0 8/26/83 Test Results 3/28/84 t-T3344-BA025 480V MCC Bus 32-3A 0 8/26/83 Test Results 3/28/84 T3344-BA02 V MCC Bus 32-1P 0 8/26/83 Test Results 6/14/84 T3344-BA027 480V MCC Bus 32-2P- 0 8/26/83

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' Test Results 3/28/84-T3344-BA028 480V MCC bus 32-3P 0 8/26/83

. Test Results 3/28/84

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T3344-BA029 480V MCC Bus 32-1Q 0 8/26/83 Test Results 3/28/84 T3344-BA044 480V MCC bus 32-4G 0 8/26/83 Test Results 8/15/84

- T3344-BA045' 480V MCC bus 32-4H 0 8/26/83 Test Results 7/25/84 T3344-BA047- ~480V MCC Bus 32-30 0 8/26/83 Test Results 7/25/84 T3344-BA017 480V-MCC bus 32-1C 0 8/26/83 Test Results 6/14/84 T3344-BA018 480V MCC Bus 32-2L 0 8/26/83 Test Results 6/14/84 T3344-BA019 480V MCC bus 32-1C 0 8/26/83 1 Test Results 7/25/84

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T3344-BA020 480V MCC Bus 32-2C 0 8/26/83 Test Results 7/25/84

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? Procedure No. . Title .Rev. Approval Oate T3344-BA021 480V MCC Bus 32-1M 0 8/26/83-Test Results 7/25/84 T3344-BA022 480V MCC Bus 32-2M 0 8/26/83 1 Test Results 8/15/84 T3344-BA023 480V MCC Bus 32-1A 0 8/26/83-Test Results 3/28/84-T3344-BA024 -480V MCC Bus 32-2A- 0 8/26/83 Test.Results' 3/28/84 T3344-BA049- 480V MCC Bus 32-2Q 0 8/26/83

. Test Results 6/14/84 LT3344-BP030 480V MCC bus 32-1T 0 6/24/83 Test Results 7/31/84 T3344-BP031- -480V MCC Bus 32-2T 0 8/23/83 Test Results 7/31/84 T3344-BP032 480V MCC bus 32-3T 0 8/23/83 Test Results 7/31/84 T3344-BP033 480V MCC Bus 32-4T 0 8/23/83 Test.Results 4/6/84 T3344-BP034 480V MCC Bus 32-5T 0 8/23/83 Test Results 4/6/84 T3344-BP035 480V MCC Bus 32-1U- 0 8/23/83 Test Results 7/31/84 T3344-BP036 480V MCC Bus'32-20 0 8/23/83 Test Results 7/31/84 T3344-BP037 480V MCC Bus 32-3U 0 8/23/83 Test Results 7/31/84-T3344-BP038 480V MCC Bus 32-40 0 8/23/83 Test Results 7/31/84 T3344-BP039 480V MCC Bus 32-5U 0 8/23/83 Test Results 7/31/84

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' Procedure No : Title'

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. Rev.' Approval Date-HT3344-BP040 -480V MCC Bus 32-1 /23/83-

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Test Results~ 7/31/84 T3344-BP041 ~480V MCC Bus 32-2R 0 8/23/83-Test Results- 7/31/84 1T3344-BP042; '480V MCC1 Bus 32-1W 0 8/23/83 Test Results- 7/31/84 T3344-BP043 .480V MCC Bus 32-2W 0 8/23/83

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Test Results 7/31/84 T3344-BP046 480V MCC Bus 32-20 0 8/23/83

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1 Test-Results 7/31/84-

T3344-BP048 480V.MCC Bus 32-3L 0 8/26/83

' Test Results 11/26/84 T3344-BP050- 480V MCC Bus 32-1K 0 1/31/85 Test Results 8/14/85 T3347-AP001 LReserve Station Service Transformer 15G-23SA 0 8/23/83

. Test Results 4/2/8 T3347-AP002 Reserve Station Service Transformer 15G-23SB 0 10/24/84 Test Results 7/12/85

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T3347-CA' Main Generator Stepup Transformer 15G-3XA/B 0 7/18/85

, . Test Results 10/8/85 T33492A002 Computer Power Supply: 0 7/29/83 Test Results: '8/8/84-

'T3415-P001 Isolator Cabinet Group CESB0 0 1/20/84 Test Result /1/85 T3415-P002 Isolator Cabinet Group CESBE O 1/20/84 Test Results 10/1/85

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3-INT-2001 Computer Programs Test Appendix 3AB 1 12/5/84 Low Pressure turbine Steam Inlet Delta T Alarm H Test:Results 12/17/84

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PORC/JTG ProcedurENo;: Title

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3-INT-2001; Computer Programs-Test' Appendix 3A6 <0- 9/13/84 Pressurizer Spray Differential. Alarm

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~3-INT-2001' Computer' Programs Test Appendix 3A7 0 9/13/84

' Environmental ~ Technical Specification Alarms

' Test Results 10/5/84 13-INT-20011 ComputeriPrograms Test Appendix'3D3 0 8/23/83 Online CRT Test; Test'Results 8/26/83

, L3-INT-200 Computer Programs Test Appendix 304 0 8/19/83

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0nline Printer Tsst-

. 1 Test Results 8/26/83 3-INT-2001 ~ . Computer Pro' grams' Test Appendix 3T6 0 7/14/83

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- Computer,I/O Testing Status Test.Results 7/5/85

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23-INT-2001 Computer. Programs Test Appendix 3J8 0 7/16/84-

~ Hourly ' Data Log

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3-INT-2001 Computer Programs Test Appendix-3J10 0 1/22/85 Sequence of Events

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-3-INT-2001 ComputeriPrograms, Test Appendix 3J11' 0 1/31/84

. Diesel Generator Watt-Hour Tabulation Test'Results 7/5/85

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'3-INT-2001 ? computer Programs Test Appendix 3T2 1 7/16/85 l Engineered Safeguards System Actuation i Without Loss of Power

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' Test Results 9/17/85

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I 3-INT-2001 Computer Programs Test Appendix 3T3 1 8/8/85

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Reactor Cavity Seal' Ring-Test Results 7/30/85

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' Attachment.C' 10

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PORC/JTG-Procedure No. ' Title Rev. Approval Date 3-INT-200 Reactor Cavity Seal Ring 0 3/6/85 Test Results '7/30/85 ib - T3402-A Reactor Coolant Pump Vibration Monitoring 0 2/21/85

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- _ Test Results 10/11/85

~ 3-INT-2001l Computer Programs Test Appendix 3A8 1 12/15/84 Condenser Vacuum Differential Alarm Test Results 6/6/85 3-INT-2001 . Computer Programs Test Appendix 3Al 0 5/6/85 Deviation in-Redundant Measurements Test'Results 9/10/85

'3-INT-2001 Computer Programs Test Appendix 3A2 0 8/31/84 Reactor and-Engineered Safety Systems Protection Monitoring Test Results 9/10/85 3-INT-2001 Computer Programs Test Appendix 3J7 0 2/19/85 Analog Pre / Post Trip Review Test'Results 9/187/85 3-INT-2001 Computer Programs Test Appendix 3R4 0 12/28/84 Reactivity Parameters

, Test Results 9/27/85 T3415-P003 Isolator Cabinet Group CESBG 1 2/10/84 Test Results 4/7/84 T3415-P006 Isolator. Cabinet Group CESBP 0 1/20/84 Test Results 10/1/85 3-INT-2001 Computer Programs Test Appendix 3S1 0 10/26/84 Specific Properties of Water Test Results 12/28/84

- 3-INT-2001 Computer Programs Test Appendix 3T5 0 10/26/84 Battery / Battery Charger Testing Test Results 6/4/85 T3314HP Emergency Generator Enclosure Ventilation 0 9/12/84 Test Results 9/30/85 z-

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p, PORC/JT Procedure No. -Title Rev. Approval Date T3323CA_- EHC. Control. System' 0 2/8/84 Test Results 10/15/85 3-INT-2002 ESF Without loss of Normal Power 1 8/16/85 Test Results 10/7/85

.T3347-BA0'0 Normal Station Service XFMR 15G-3SA -0 8/5/85 Test Results 10/22/85 T3347-BA0002 -Normal Station Service XFMR 15G-3SB 0 9/6/85-Test Results' 10/22/85-

-T3339-AA: Chemical Feed - Condensate 0 6/11/85 Test Results 10/18/85 T3339-BP- Chemical Feed'- Steam Generator 'O ~ 7/30/85 Test Results 10/18/85 3-INT-2001 Computer. Programs Test Appendix 3J3 0 2/14/85 RCS Leakage Calculations Test Results 9/10/85

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~ T3301-P001 Reactor Coolant and Associated System Fill 0 3/18/85 Hydrostatic Test Test Results 10/11/85

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