ML20082U235

Draft Tech Specs Re Containment Sys Primary Containment Leakage.Related Info Encl

ML20082U235
Person / Time
Site:	LaSalle, 05000000
Issue date:	09/06/1983
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20082U163	List: ML20082U223 ML20082U235
References
FOIA-83-384 NUDOCS 8312160279
Download: ML20082U235 (21)

Text

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CONTAINMENT SYSTEMS g

PRIMARY CONTAINMENT LEAKAGE i

, LIMITING CONDITION FOR OPERATION 3.6.1.2 Primarycontainmentleakageratesshallbe}imitedto:

An overall integrated leakage rate of less than or equal to L,,

a.

0.635 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,

39.6 psig.

b.

A combined leakage rate of less than or equal to 0.60 L, for all penetrations and all valves listed in Table 3.G.3-1, except for main steam isolation valves ar.d valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests when pressurized to P,, 39.6 psig.

c.

• Less than or equal to 25 scf per hour for any one main steam

~

isolation valve when tested at 25.0 psig.

d.

A combined leakage rate of less than or equal to 1 gpm times the tota.1 number of ECCS and RCIC containment isolation valves in hydro-J statically tested lines which penetrate the primary containment, when tested at 1.10 P,, 43.6 psig.

APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Specification 3.6.1.1.-

i ACTION:

With:

P a.

The measured overall integrated primary containment leakage rate exceeding 0.75 L,, or b.

The measured combined leakage rate for al1~ penetrations and all valves listed in Table 3.6.3-1, except for main steam isolation valves and valves which are hydrostatically leak tested per -

Table 3.6.3-1, subject to Type B and C1 tests exceeding.0.60 L,,'or c.

The measured leakage rate exceeding'25 scf per hour for any one main steam isolation valve, or-d.

The measured combined leakage rate for all ECCS'and.RCIC containment isolation valves in hydrostatically tested lines which penetrate the primary containment exceeding i gpm. times the total number of'such

-30'2M, i.-

' valves,.

" Exemption to Appendix "J" of 10 CFR 50.

a v

LA SALLE.- UNIT 2 3/4'6-2:

~

t 8312160279 830906 j

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._ 9000L83 -384_,._ PDR _ m.

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CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) g

, restore:

The overall integrated leakage rate (s) to less than or equal to 0.75 a.

L, and a

b.

The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam isolation valves and valves which are hydrostatically leak tested per Table 3.6.3-1, subject to Type B and C tests to less than or equal to 0.60 L,, and The leakage rate to less than or equal to 25 scf per hour for any c.

one main steam isolation valve, and d.

The combined leakage rate for all ECCS and RCIC containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, prior to increasing reactor coolant system' temperature above 200*F.

SURVEILLANCE REOUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - 1972:

Three Type A Overall Integrated Containment Leakage Rate tests shall a.

be conducted at 40 10 month intervals during shutdown at P,,

39.6 psig, during each 10 year service period. The third test of each set shall be conducted during the shutdown for the 10 year-plant inservice inspection, b.

If any periodic Type A test fails to meet.75 L,, the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.

If two consecutive Type A tests fail to meet.75 L,,

a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet.75 L,, at which tirue the above test schedule may be resumed.

The accuracy of each Type A test shall be verified by a supplemental c.

test which:

1.

Confirms the accuracy of the test by verifying that the difference between the supplemental data'and the Type A test data is within 0.25 L,.

2.

Has duration sufficient to establish accurately the change in t

l leakage rate between the Type A test and.the supplemental test.

3.

Requires the quantity of gas injected into the containment or

,(

bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage l

at P,, 39.6 psig.

LA SALLE - UNIT 2 3/4 6-3

o-N' '8 CONTAINMENT SYSTEMS l

SURVEILLANCE REOUIREMENTS (Continued) d.

Type B and C tests shall be conducted with gas at P,, 39.6 psig*, at intervals no greater than 24 months except for tests involving:

1.

Air locks, 2.

Main steam line isolation valves, 3.

Valves pressurized with fluid from a seal system, and 4

ECCS and RCIC containment isolation valves in hydrostatically tested lines which penetrate the primary containment.

e.

Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

i '

f.

Main steam line isolation valves shall be leak tested at least once per 18 months.

g.

Liakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P,,

I 43.6 psig, and the seal system capacity is adequate to maintain system pressure'for at least 30 days.

h.

ECCS and RCIC containment isolation valves in hydrostatically tested lines which penetrate the primary containment shall be leak tested at least once per 18 months.

i.

The provisions of Specification 4.0.2 are not applicable to 24 month or 40 10 month surveillance intervals.

"Uniess a hydraulic test is required per Table 3.6.3-1.

LA SALLE - UNIT 2 3/4 6-4 r-----

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LASALLE UNIT 2 16 32832 THU. 30. JN 1983 eene SutirtARY OF DATA SETS 20 THku 35 enae

.~.. --

i DATA TEST TAPE TEff.

DRY AIR ttEASURED CALCULATED PEAS LEM RALE CALC LEM 95% UPPER.'

CY nURATIrw Ytar rgs pgrnimr MASS

.ttASS. _ _.. TOTAL PolHL.

RATF C0tFIDENfT (HRS)

(PSIA)

T=0

% / DAY Z / DAY

% / DAY LIMIT 20_._D.000003 _D3I42500 _544.77673 _53.39452__1.04416E+05.

U.00000E-01

.0.U000 __.__0.0000.

0.0000

.0.0000 _

21 0.333336,04:02:00 544.73926 53.33770 1.04312E+05 0.00000E-01 7.1670 7.1670 0.0000 0.000f) t j

22 0.666668 04:22800 544.72205 53.37737 1.04393E+05 1.04305E+05 0.7951

-5.5823 0.7954 18.6995 e.

3 M '1.0000nrt n&1422nn N44.68213

• a W AM 1.D4307Et01_1.04394E+05 2.49Y3 NYDE9 1 -4Wn a.5685 24 1.333336 05:02:00 544.64758 53.318Y5 1.04293E+05 1.043Y4E+05 2.1214 0.9890 1.7306 4.0594 25 1.666668 05:22:00 544.63Y53 53.31987 1.04296E+05 1.0438vE+05 1.6508

-0.2319 1.4614 2.888/

,._ __26._2.00000Q 05142100. 544.6 '219_53.32770._.1.04315E+05. 1.04380E+05 1.1598

-1.2Y66 1.0699.

2.1283 27 2.3333?6 06:02:00 544.59875 53.30/33 1.04283E+05 1.04378E+05 1.3054 2.1806 0.Y992 1.7644

,i-28 2.666663 06:22:00 544.58228 53.31986 1.04307E+05 1.04371E+05 0.9375

-1.6398 0.7904 1.4119~

{ 1 29 1.000000__D M 42

nn 544.56665__iL 24190._1.04197Et 05-__.J. 04381 E+05 1.6792 7.621Q 1.0563 1.6205

- ~,'-

30 3.333336 07:02:00 543.48938 53.27776 1.04434E+05 1.04353E+05

-0.1272

-16.4198 0.4085 1.2313 31 3.666668 07:22:00 543.40344 53.242Y6 1.04383E+05 1.04340E+05 0.2084 3.5646 0.1560 0.8828

,._ _ 32_4.UQ0nnn D7142300._543.10374._53.24874._1.04452E+05. 1.04324E+05

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33 4.S33336 08:02:00 543.07410 53.26663 1.04492E+05 1.04308E+05

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LASALLE UNIT 2 12:10:01 iFRI. 01 JUL 1983 s

SUMMARY

OF DATA SE 73 THRU 87 M***

DATA TEST' TAPE' TEPP DRY AIR HEASURED C CULATED MEAS LEAK RATE CALC LEAK 95% UPPER grT DURATIoM TfMr e ' 91 -

RRrmiter MAnn -

' MARS TnTN

__. PnfMT DAIE f'nNFIDENEF (HRS)

(PSIA)

T=0

% / DAY

% / DAY

% / DAY LIMIT s

1 79 n_nnnnnn n7:pp:nn 549.9137n 54.14259 1.n6256EiO5 n-00000E-01 D.D0D0 0 0000 0 0000 0 D000 2 74 0.333336 I07842 00 542.87463 54.15316.1.06276E+05'y0.00000E-01' 54.14911: 1.06263E+05'

-0.4531 ' ' -0.4531?

10.0000' O.0000 Y 75 0.666672 08202:00 542.84546 g.1.06255E+05

-0.6898

. -0.9264;'

-0.6898.

-0.0251

'I 7A

-4 nnnnnnsrinnoornn M42 R7451 M4.151MA."4_nADA7K4MM "'i.0A25RF+nM.

-n _9AnM -

0.M?91 i +.D 9970.

_ n.2H9A I 77 1.333336 08:42:00 542.89001 54.14899 1.06259E+05 1.06262E+05

-0.0588 0.5463

1. 0.0967 0'g6 ' O.3651

-0.0798 C 78 1.666672 09:02:00 542.92249 54.14725 1.06250E+05 s1.06265E+05 0.0853 0.6617 O.4394 t

Z,79 P.0n0000 09:?2:nD 542_9892A 54.14P91 1.DAPPRF+05 1.0627nE+n5 0.3150 1.4A33 L D.37,62 0.6409 8 80 2.333336 09:42:00 ^543.01270 J,54.14108 $.06220E+05 2 %06274E+05 W0.3491 W 0.5539? ' iO.4140 p W" O.6834 Y 81 2.666672 10 02:00 / 542.99170 54 1392741 s06220E+05 A L 1606274E+05 ' M O.3006V--U.0392L 0.4342 - N 0.6388

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// 83 3.333336 10.42:00 543.02502 54.13722 1.06210E+05 1.06274E+05 0.3120 0.6916 0.4277 0.5572

/.'l 84 3.666672 11:02:00 543.03113 54.13374.1.06202E+05 ' 1'.06274E+05

.0.3332 0.5455 OJ355 0.5423 I

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GLEN ELLYN ILLINOIS 6tr137

'JUL 2 8 1983 Docket No. 50-373 Docket No. 50-374 Commonwealth Edison Company ATTN:

Mr. Cordell Reed Vice President Poc,t Of fice Box 767 Chicago, IL 60690 Gentlemen:

This refers to the routine safety inspection conducted by Messrs. S. G. DuPont, L. A. Reyes, R. D. Lanksbury, and G. C. Wright of this office on June 20 through July 22, 1983, of activities at the LaSalle County Nuclear Station, Units 1 and 2, authorized by NRC Operating License No. NPF-11 and NRC Construction Permit No. CPPR-100 and to the discussion of our findings with Mr. G. J. Diederich at the conclusion of the inspection.

The enclosed copy of our inspection report identifies areas examined during

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the inspection. Within these areas, the inspection consisted of a selective examination of procedures and representative records, observations, and interviews with personnel.

During this inspection, certain of your activities appeared to be in noncompliance with NRC requirements, as specified in the enclosed Appendix, A written response is required.

In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure (s) will be placed in the NRC Public Document Room unless you notify this office, by telephone, within ten days of the date of +.his letter and submit written application to withhold information contained therein within thirty days of the date of this letter. Such application must be consistent with the requirements of 2.790(b)(1).

If we do not hear from you in this regard within the specified periods noted above, a copy of this 3etter, the enclosure (s), and your response to this letter will be placed in the Public Document Room.

The responses directed by this letter (and the accompanying Notice) are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511.

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We will gladly discuss any questions you have concerning this inspection.

t Sincerely.

" Original Sfsned by J. F. Strc'eter" J. F. Streeter, Chief Engineering Branch I

Enclosures:

1.

Appendix, Notice of Violation 2.

Inspection Reports 50-373/83-28; 50-374/83-23(DE) cc w/ encl:

D. L. Farrar Director of nuclear Licensing D. L. Shamblin, Site Construction Superintendent T. E. Quaka, Quality Assurance Superintendent G. J. Diederich, Station

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Superintendent R. H. Eolyoak, Project Manager DMB/ Document Control Desk (RIDS)

Resident Inspector, RIII Phyllis Dunton, Attorney General's Office, Environmental Control Division l

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i Appendix NOTICE OF VIOLATION Commonwealth Edison Company

. Docket No.-50-373 Docket No. 50-374 As a result of the inspection conducted on June 20 through July 22, 1983, and in accordaace with the NRC Enforcement Policy, 47 FR 9987 (March 9, 1982), the following violations were identified:'

1.

10 CFR 50, Appendix B, Criterion XI,' states, in part, " Test procedures shall include provisions for assuring that all prerequisites for the given test have been met...".Startup Manual Procedure, LSU 400-1, Appendix A. Section 5.0, states, in part, "Tr,st. conditions which are different than those expected during normal or accident operation should be justified and documented in the system initial conditions and prerequisites section." Startup Manual Procedure, LSU 500-1,

,l Section F.5, states, in part, "The System Test.. Engineer shall be responsible for verifying that prerequisites are satisfied prior to commencing a test."

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Contrary to the above, a test condition existed that.was different than-those expected during normal or accident operation without being documented in the system initial conditions and prercquisites-section of the Low Pressure Coolant. Injection test portion of the Residual Heat Removal System Prc:perational Test Procedure, PT-RH-201, in that the automatic iM tiation mode of the "B" and "C" loops of RHR.

were defeated by the Unit Separation Criteria. Additionally..the System Test Engineer failed to verify that the prerequisites of PT-RH-

-g 201, specifically those that were impacted by the Unit Separation Criteria were satisfied prior to commencing tha-test.=

This is a Severity Level IV violation (Supplement II).

- 2.

10 CFR 50,' Appendix B, Criterion V, states,'in part, " Activities.

j affecting quality shall be prescribed by documented instructions,

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procedures, or drawings...and shall be accomplished in-accordance.

with these instructions, procedures, or. drawings."~

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- - Contrary to the above, the following instances were noted'during the.

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_ ' performance of the Containment Integrated Leak Rate' Test (CILRT) where an activity affecting quality was not: accomplished'in'accordance with an approved procedure:'

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Appendix 2

a.

Contrary to station test procedure LTS 300-4, the air supply header was vented and the spool-piece connecting the charging line to the containment spray line was removed prior to the completion of temperature stabilization.

b.

Contrary to station test procedure LTS 300-4, no entries were made in the CILRT events log between 2120 houra on June 28, 1983, and 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on June 29, 1983, even though actions were taken such as those noted in Item a above, that should have been logged.

This is a Severity Level V violation (Supplement II).

3.

10 CFR 50, Appendix B, Criterion XIV, states, in part, " Measures ~shall also be established for indicating the operating status of structures, systems, and components of the nuclear power plant..., such as by tagging.

valves and switches, to prevent inadvertent operation."

Contrary to the above following completion of the licensee's valve lineup for the CILRT, the inspectors found that the Jet Pump Instrumentation Stop Valves in the TIP room had not been tagged to prevent inadvertent operation.

This is a Severity Level V violation (Supplement II).

Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement or explanation in reply, including for each item of noncompliance:

(1) cor-rective action taken and the results achieved; (2) corrective action to be taken to avoid further noncompliance; and (3) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.

'JUL 2 81983 gg_

Dated J.-T, Streeter, Chief Engineering Branch 1 M

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m U. S. NUCLEAR REGULATORY COMMISSION REGION III Reports No.

50-373/83-28(DE); 50-374/83-23(DE)

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Dogket Nos.

50-373; 50-374 Licenses No. NPF-11; CPPR-100 Licensee: Commonwealth Edison Company Post Office Box 7o7 Chicago, IL 60690 Facility Name: LaSalle County Station, Units 1 and 2 Inspection At: LaSalle Site, Marseilles, IL Inspection Conducted: June 20, 1983 through July 22, 1983 j

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9 WE Approved L. A. Reye.

hief Da'te Test Prog s Section Inspection Summary Inspection on June 20 through July 22, 1983 (Reports No. 50-373/83-28(DE);

50-374/83-23(DE))

Areas Inspected: Routine, unannounced inspection of preoperational test procedures; preoperational test procedure verification; preoperational test witnessing; preoperational test results review and verification; containment integrated leak rate test; and review of startup test results and licensee's evaluation of test results. The inspection involved a total of 248 inspector-hours, onsite by four inspectors including 74 inspector-3 hours during off-shifts.

Results: Of the seven areas inspected, no items of noncompliance or deviations were identified in five areas. Within the remaining areas, three items of noitcompliance were identified (failure to follow procedure - Parap,raph'3.b.;-

a failure to follow procedure - Paragraph 8.c.; and failure to tag ifalves -

Paragraph 8.d.).

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DETAILS 1.

Persons Contacted

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• D. Farrar Director, Nuclear Licensing

• R. H. Holyoak, LaSalle Project Manager

+*R. D. Bishop, Administrative and Support Services Assistant Superintendent

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C. Renwick, Technical Staff Supervisor

• W. R. Huntington, Assistant Technical Staff Supervicor

• E. J. Stevak, Acting Quality Assurance Supervisor

• J.

A. Ahlman, Quality Assurance

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R. Pfister, Test Engineer

• T. Hammerich, Test Engineer

• R. Koenig, Test Engineer

• Me D. Shaible,-Test Engineer The inspectors also interviewed other licensee employees including members of the quality assurance, technical, construction, and operating staff.

+ Denotes personnel' attending exit interview on July 15, 1983.

• Denotes personnel attending exit interview on July 22,.1983.

2.

Preoperational Test Procedure Verification - Unit 2 The inspector verified that the following preoperational test procedures

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were written,. reviewed, and approved by.the licensee in accordance with

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the requirements of the Regulacory Guide 1.68 and~the QA Manual.

i a.

SD-CD-202 Condenser System b.

SD-CQ-201-Communications System c.

SD-CY-201 Cycled Condensate Supply System -

d.

SD-FW-202 Feedwater Control System e.

PT-VP-203 Primary Containment HVAC System f.

PT-VX-201 Switchgear Heat Removal System g.

SD-WS-201 Service Water System; No items of noncompliance or deviations were identified.~

3.

a Preoperational' Test Witnessina - Unit 2 The following Preoperational Tests were witnessed during-this inspection; period:

s.

PT-MS-201A Main Steam Leakage Control System The inspector witnessed the Low Dilution Air Flow Interlocks and Valve Test Mode Lockout ~ Verification portions of the Main'Steas Leakage Control)

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System preoperational test'to' ascertain through.observatlon and record;

.. review that testing was conducted ~in accordance with approved procedures.

Additionally, the performance'of licensee personnel was evaluated during the test.

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The major objective of the test was to verify system operation with L

low dilution air flow. The inspector verified that the testing requirements of the FSAR were satisfied in all cases. The inspector also reviewed the system turnover package to verify the aystem test boundaries.

.b.

PT-RH-201,' Residual Heat Removal (RHR) 1 The inspector witnessed the Low Pressure Coolant Injection (LPCI) portion of the RHR preoperational test to ascertain through observation, record review, and independent' calculations that testing was conducted in accordance with approved and technically adequate procedures.

t The major objectives of the test were to verify system oparation in i

both the manual and automatic initiation. modes'and to calculate the net positive suction head of the system pumps.

4 During.the performance of the LPCI operation test of loops "B" and "C",

the System Test Engineer (STE) was unable to simulate a high drywell pressure as required by the preoperational test procedure with the Drywell High Pressure Relays 2E12-K5 and 2E12-K6. The STE determined by visual inspection that leads had been lifted to prevent the actuation of Relay 2E12-K6 and that the lif ted leads were part of the unit separation-required to prevent inadvertent starts of the 2A Diesel Generator during Ur.it 2 testing. The STE revised the procedure to continue testing'and

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LPCI Injection Valves by using the Manual Initiation Switch at panel to accomplish the objective of observing the. automatic operation of.the i

2H13-P601 in the control room. However, the Manual' Initiation Switch also failed to actuate either the "B" or "C" loop LPCI Injection Valves.

The STE's inspection revealed that the Manual' Initiation Switch was-included in the unit separation to prevent inadvertent operation of the 2A Diesel Generator during Unit'2 testing. 'With the exception of the 4

t.utomatic initiation, the preoperational test was completed-satisfactorily.

4 The inspector determined through discussions with licensee personnel; and record review that the Unit Separation Criteria was ' accomplished-by lifted leads, installed jumpers, and tagouts prior to the completion-of the review and' approval of the preoperational test procedure.

Information pertaining to this unit separation _was not documented.in the system condition and prereq21 site section of.PT-RH-201 during the f

review and approval ~ process.as required by Startup. Manual _ Procedure ~

l LSU 400-1, Preoperational Test and System Demonstration' Procedures,-

1 which states that test' conditions which are differentL than' those -

l expected during normal or accident operation should be justified and.

i-documented in the prerequisite section of the procedure. The leads l

that.were lifted for unit'eeparation resulted?in a condition ~not considered'as either a normal or accident operation moder.--

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i Additionally, the STE failed to establish the system test boundaries of the prerequisites prior to commencing testing as required by Start-up Manual Procedure LSU 500-1, Use of Test Procedures, Section F.5.,

which states that STE is responsible for verifying that, prerequisites are satisfied prior to commencing a test. This is considered to be an item of noncompliance (374/83-23-01(DE)).

With the exception of the automatic initiation mode, the inspector verified that the testing requirements of the FSAR were satisfied.

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The inspector discussed with the licensee concerns pertaining to the impact of unit separation on other preoperational testing, specifically PT-AP-203, Emergency Power Redundancy Preoperational Test. At a meeting with the STEs, the licensee addressed the inspector's concerns of the impact of unit separation on related preoperational testing.

Additionally, the specific impact on PT-AP-203 was discussed with the cognizant STE to ensure that unit separation will not effect testing conditions.

No other items of noncompliance or deviations were identified.

4.

Preoperational Test Results Review - Unit 2 The inspector reviewed the results of the following test procedures against the prescribed acceptance criteria and reviewed the licensee's test evaluation for adequacy:

PT-AP-202 DC Distribution Preoperational Test PT-VP-201 Primary Containment Vent and Purge Preoperational Test These procedures were found satisfactory.

No items of noncompliance or deviations were identified.

5.

Preoperational Test Results Verification - Unit 2 The inspector reviewed the results of the following preoperational test procedures against the acceptance criteria and reviewed the licensee's test evaluation for. adequacy:

a.

PT-VX-201 Switchgear Heat Removal b.

SD-CQ-201' Communications Systems c.

SD-WS-201 Service Water d.

SD-CD-202 Condenser e.

SD-CY-201 Cycled Condensate i

~ - These procedures and their evaluations were found satisfactory. unless otherwise noted.

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During the review of the Cycled Condensate System Demonstration, the j

i inspector discovered two different final pages in the procedure's 1

evaluation. Both pages included in their summaries a listing of out-standing deficiencies required to be completed prior to Unit,2 fuel load l

(Category 1). However, the two listings were different in th_at Deficiency SD-CY-201-43 on the Cycled Condensate Heat-trace Heater no. 508 was omitted on one listing.

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Discussions with the STE revealed that during the on-station review of

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the system demonstration evaluation, the deficiency was determined not to be a Category 1 and did not require completion prior to unit fuel load.

The STE revised the evaluation by rewriting.the final page and omitting the deficiency from the summary. However, the STE did not make any notations to indicate that the revised page was the correct and most current revision.

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Additionally, the inspector determined that the evaluation review conducted-by the Project Engineering ~ Department (PED) was performed on the. incorrect-summary page. PED's review indicated that Deficiency SD-CY-201-43 was classified as Category I based upon the STE's evaluation and that the deficiency shall be resolved during a special test, LST 83-11. Even though PED's review was correct, the review was performed on an inaccurate evaluation provided to PED from the station. The evaluation and sunmary is considered to be part of the preoperational test and system demonstration procedures and the controls established for revising a procedure also apply to changes to the evaluation and sumary of the procedure. The inspectors will verify the application of proced.are change controls when future changes-are noted to evaluations and summaries of tests.

No items of noncompliance or deviations were identified.

6.

Review of Startup Test Results - Unit 1 t-The inspector reviewed the results of the following startup tests performed during Test Condition number 3 (50%'to 75% control rod lines with core flow l

greater than 80%) and determined that all test changes were processed-in-4 accordance with the Technical Specifications;' test deficiencies were processed and corrected as required; data sheets were complete and deficiencies noted;-

results were evaluated and met'the acceptance criteria; and the results.

.were reviewed'and approved by. station and corporate management'as required, unless otherwise noted:

STP-18' Core Power Distribution STP-19 Core Performance i_

During review of STP-19, the inspect'or-determined that'the value'for.ratedL i

total core-flow that the process computer.used was~106.5'Mlb/hr rather than'

' 1108.5 Mlb/hr given in the Technical Specification. The use of the lower J

total core flow constant'resulted in a nonconservative critic.a1 power" ratio (CPR) limit and as such :it. appeared ~ the unit had the potential. for operating ;

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ks Subsequent to the July 15, 1983 exit, the licensee revised the constants utilized in the process computer equation for computing the CPR flow correction. The inspector reviewed this change and determined that it satisfied his immediate concern. However, the question of whether or not the o;,. rating minimum CPR limit has ever been exceeded remains. The

- licen'ee has agreed to evaluate this matter. This is considered an

. unreso '.ved item for Unit 1 (373/83-28-01(DE)) pending evaluation by the licensee. This is considered to be an open item for Unit 2 (374/83-28-02(DE)) pending the licensee's resolution of this concern by taking the same action as for Unit 1.

No items of noncompliance or deviations were identified.

7.

Review of Licensee's Evaluation of Test Results - Unit 1 The inspector reviewed the results of STP-12, APRM Calibration, performed during Test Condition 3 and determined-that the resnits were evaluated and met the acceptance criteria; and that the results were reviewed and approved by station management as required.

No items of noncompliance or deviations were identified.

8.

Containment Integrated Leak Rate Preoperational Test - Unit 2 a.

Procedure Review The inspector reviewed procedure LTS 300-4, Revision 5, Unit 1/2 Integrated Primary Containment and Drywell Floor Bypass Leak Rate Test, and verified that the procedure was technically adequate'and-consistent with regulatory requirements, except as noted below.

Paragraph E.9 states that during the temperature stabilization period containment pressure is required to be kept at 39.6 + 0.5 O psig.

Paragraph F.2.e lists the criteria for containment pressure during temperature stabilization as 39.6 + 1.0

.0 psig.: The 39.6 + 1.0 -

O psig value is the one utilized during the performance of the test

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and the licensee has connitted to change Paragraph E.9 to reflect this prior to the next use of-LTS 300-4.

Since this is a joint unit procedure, this is considered to be an open item (373/83-28-02(DE))

pending the licensee completion of the revision effort prior to its

-use on Unit 1.. The inspector also noted during the conduct of the test that since LTS 300-4 does not. require recording ofLthe barometric pressure during the temperature atabilization period'and since the computer printouts of containment pressure are in absolute pressure.:

there is no documentation to show that containment pressure is maintained within the required band. However, the _ inspector did verify during :

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"The-licensee-the conduct of the test that this, requirement was met. -

I has committed to revise LTS'300-4 prior to its next'use to correct.

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This is considered an open item (373/83-28-03(DE)) pending the I

licensee's completion of the revision effort prior to its use on Unit 1.

b.

Instrumentation The inspector reviewed the calibration data associated with performing the CILRT.

A multipoint calibration of all instrumentation was per-formed. Correction values were generated based on the difference between measurements of resistance from a NBS verified resistance box and actual resistance measured. All corrections were placed as an array or equation into the CILRT computer.

The following instrumentation was used in the CILRT:

Ty.pe Quantiy RTDs 28*

Flowmeter 1

Pressure Gauge 2

Dewtells 6

During the test, one of the RTDs in subvolume 8 became defective.

For the duration of the test, its reading was removed from the average temperature calculated from the other five sensors in this subvolume.

• Does not include the def ective RTD in subvolume 8.

c.

Witness of Test The inspectors witnessed portions of the CILRT on June 29 through July 2, 1983 and verified that:

Appropriate revision of procedure was in use by test personnel.

Test prerequisites were met.

Proper plant systems were in service.

While witnessing the pressurization and subsequent temperature stabilization, the inspector noted two instances in which the approved procedure for the CILRT was not strictly adhered to.

The first instance occurred approximately two hours into the first temperature stabilization period, when the inspector noted that the spool-piece connecting the charging line, from the air compressors used to pressurize the containment to the containment spray line was being emoved.

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Station procedure LTS 300-4, Unit 1/2 Integrated Primary Containment and Drywell Floor Bypass Leak Rate Test, referenced by PT-PC-201 to perform the CILRT, step F.2.e.,

requires a minimum of four hours for

emperature stabilization.

Step F.2.f. states that when stabilization is complete, vent the air supply header and remove the spool-piece.

Since only about two hours had elapsed at the time of the removal of the spool-piece and since step F.2.e. requires a minimum of four hours to stabilize temperature, the procedure was obviously not parformed in sequence.

This is considered to be an example of an item of noncompliance (374/83-23-03A(DE)).

The second instance occurred when the inspector noted on review of the CILRT events log that no entry had been made between 2120 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.0666e-4 months <br /> on June 28, 1983, and 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on June 29, 1983, when the inspector's review was performed.

Paragraph C.1 of LTS 300-4 states that a signed and dated events log must be kept up to date at all times by the cognizant engineer on shift.

This requirement is again reiterated in Paragraph E.13 of LTS 300-4 and with the additional requirement that the log shall be updated at least once per shift. During the time that no entries were made in the events log a number of actions were performed which should have been logged, including venting of the air supply header and removal of the spool-piece connecting the charging line to the containment spray line. This is considered to be an example of an item of noncomplian.3 (374/83-23-03B(DF)).

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The inspectors also noted that the temperature survey required by

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Faragraph 7.4 of ANSI N45.4-1972 had not been performed.

The inspectors found that on Unit I the Architect Engineer (Sargent & Lundy) had performed an engineering evaluation to determine sensor placement.

Subsequently, based on comments by both the licensee and the NRC, modifications were made as to the number of sensors and their locations.

These same locations were used for Unit 2, as allowed by ANSI N45.4.

In addition, since the unit is still under construction there are basically no heat loads of any significance at this time as would be the case for an operating plant.

The licensee has been inf o rmed that prior to performing the next CILRT, the temperature survey will be required to substantiate placement of the required sensors.

This is considered to be an open item (373/83-28-04(DE)) pending the licensee's completion of the temperature survey.

d.

Direct Observation of Valve Lineups The inspector verified by direct visual observations that valve lineups were completed in accordance with the test procedures with the following exception.

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During a walkdown of the completed valve lineups, the inspectors found that the Jet Pump Instrumentation Stop Valves (2B21-F456, F458, F460, F462, F464A, F464B, F466, F468, F470, F472,-F474A, and F474B) in the TIP room were not tagged. Paragraph C.10 of LTS 300-4 states that all valves associated with the CILRT should be tagged. Even though this prerequisite is worded as a "should" versus a "shall", the inspector considers it a requirement in that 10 CFR 50, Appendix B, Criterion XIV states, in part, " Measure shall also be established for indicating the operating status of structures, systems, and components of the nuclear power plant..., such as by tagging valves and switches, to prevent inadvertent operation."

The inspectors verified the position of the valves to be in the closed position as required.

The valves were subsequently tagged after the inspectors pointed out to the licensee the lack of tagging.

This is considered to be an item of noncompliance (374/83-23-04(DE)).

e.

CILRT Valve Lineup Penalties The valve configurations for Instrument Air, LPCS, and HPCS systems deviated from the normal CILRT valve lineup. As a result, the local leak rate test results shall be added as a penalty to Lam at the 95%

confidence level. However, all of the licensee's calculations were not completed during this inspection period and will be followed by the inspector.

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f.

CILRT Data Evaluation The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> CILRT was started on July 1,1983, at 7:22 am.

The inspectors independently monitored and evaluated leak rate data to verify the licensee's calculations of the leak rate. There was acceptable agreement between the inspectors' and licensee's leak rate calculations as indicated in the following summary (units are in weight percent per day):

Measurement Licensee Inspector Leakage rate measured (Lam) 0.1927 0.1926 during CILRT Lam at 95% confidence level 0.1999 0.1998 Lam at 95% confidence level adjusted to reflect penalties (refer to Paragraph 8.e.)

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1 Appendix J acceptance criterion at 95% confidence level = 0.75 La =

0.75 (0.635) = 0.476.

As indicated above, the penalties required to calculate the adjusted Lam at the 95% confidence level were nc available at the time of this report. Final evaluation.of the CILRT results is considered an open item (374/83-23-05(DE)) pending completion of the inspector's review of the penalties relating to valve configura-tion deviations.

Supplemental Test Data Evaluation g.

After completion of the 24-hour test on July 2, 1983, a known leakage of 0.5418 weight percent / day was induced.

The inspectors independently monitored and evaluated leak rate data to verify the licensee's calcu-lation of the supplemental leak rate. There was acceptable agreement o

between the inspectors' and licensee's leak rate calculations as indicated in the following summary (units are in weight percent per day):

Measurement Licensee Inspector Measured leakage (Lc) rate 0.5721 0.5727 during supplemental test Le at 95% confidence level 0.5992 0.5995 Induced leakage rate (Lo) = 0.5418 0.5302 Appendix J acceptance criterion: Lo + Lam - 0.25 La < Le < Lo + Lam +

0.25 La.

As indicated above, the supplemental test results satisfied the requirements of 10 CFR Part 50, Appendix J.

No other items of noncompliance or deviations were identified.

9.

Open Items Open items are matters which have been discussed with the licensee, which uill be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee or both. Open items disclosed during the inspection are discussed in Paragraphs 6, 8a (two), 8c, and 8.f.

10.

Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. An unresolved item disclosed during this

, inspection is discussed in Paragraph 6.

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Exit Interview on July 15, 1983

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The inspector met with licensee representatives.(denoted in Paragraph 1)

. on July 15, 1983, and sunmarized the scope and findings of the inspection on Unit 1 startup activities. The licensee acknowledged the-inspector's Comments.

12.

Exit Interview on July 22, 1983 The inspectors met with licensee representatives (denoted in Paragraph 1) on July 22, 1983, and summarized the scope and findings of the Unit 2 preoperational inspection activities. The licensee acknowledged the statements by the inspectors with respect to the items of noncompliance (Paragraphs 3.b., 8.c., and 8.d.).

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