IR 05000454/1986006

Insp Repts 50-454/86-06 & 50-455/86-05 on 860204-06.No Violations or Deviations Noted.Major Areas Inspected: Preoperational Gaseous & Liquid Radwaste,Including Status of Certain Preoperational Demonstrations & Tests of Sys

ML20214E160
Person / Time
Site:	Byron
Issue date:	02/27/1986
From:	Hueter L, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20214E153	List: IR 05000454/1986006 ML20214E150
References
50-454-86-06, 50-454-86-6, 50-455-86-05, 50-455-86-5, NUDOCS 8603070158
Download: ML20214E160 (5)

Text

.

.,

U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-454/86006(DRSS);50-455/86005(DRSS)

Docket Nos. 50-454; 50-455 Licenses No. NPF-37; CPPR-131 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Byron Station, Units 1 and 2 I

Inspection At: Byron Station, Byron, IL Inspection Conducted: February 4-6, 1986

~~7)/dj$amd$o Inspector: L. J. Hueter MJM/6 Date Approved By:

'?)///$Iw"A U M. C. Schumacher, Chief NM/'

Radiological Effluents Date and Chemistry Section Inspection Summary Inspection on February 4-6, 1986 (Reports No. 50-454/86006(DRSS);

50-455/86005(DRSS))

Areas Inspected: Routine, unannounced inspection of preoperational gaseous and liquid radwaste program for Unit 2, including: status of certain preoperational demonstrations and tests of systems, post test evaluations, and resolution of deficiencies. The inspector also reviewed licensee actions regarding a previous citation involving Unit 1 and regarding two previous open items involving both Units 1 and 2. The inspection involved 22 inspector-hours onsite by one NRC inspecto Results: No violations or deviations were identifie G603070150 860220 PDR ADOCK 05000454 G PDR

'

.

DETAILS 1. Persons Contacted

• Barrett, Rad / Chem Staff

• Britton, QA Inspector

• Chernick, Compliance Supervisor

• Falb, Unit 2 Testing Supervisor F. Hornbeck, Technical Staff Supervisor

• J. Langan, Compliance Staff J. Van Laere, Rad / Chem Supervisor

• R. Ward, Services Superintendent

• K. Weaver, Station Health Physicist

• C. Zola, QA Engineer

• R. Waters, SET Engineer, Westinghouse

• P. Brochman, NRC Resident Inspector J. Hinds, Jr., NRC Senior Resident Inspector The inspector also contacted other licensee personne * Denotes those present at the exit meetin . Licensee Action on Previous Inspection Findings (Closed) Violation (454/85038-02(DRSS)): Failure to take timely action when a Technical Specification LC0 release limit was exceeded. As noted in subsequent Inspection Report No. 50-454/85051, the licensee's initial response asserted that the violation was predicated on a misunderstanding by the NRC and, furthermore, that an analysis not previously available for NRC review demonstrated that the release was adequately diluted before release to the river. On these bases, the licensee requested withdrawal of the citation. In consideration of this request, we responded by clari-fying the basis for the citation and requested submission of the referenced analysis for our further evaluation. By letter dated February 4, 1986, the licensee submitted a summary of an analysis showing mixing of the liquid radwaste with the circulating water blowdown, while traveling to the end of the blowdown line (approximately 2.5 miles long)..in transit to the river. We were unable to make a thorough review of the evaluation because insufficient detail was provided regarding the bases for the analysis. However, the final result of the evaluation appears to be that the liquid waste discharge was diluted in 30,500 gallons of water over a dispersion length of 577 feet. Inasmuch as the liquid waste discharge was 2700 gallons with a concentration of about 30 times MPC, this dilution would only reduce the average concentration in the release to approximately 2.6 times MPC. Based on this consideration, the withdrawal of the citation would be inappropriate. A review (described in Inspection Report No. 50-454/85051) of corrective actions taken in response to a related

____ __ - . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ _ _- _ __________-__ __

., '.

citation (Violation 454/85038) appears to appropriately address corrective action to preclude recurrence of the problem leading to this citatio These actions included two procedural changes, a control room posting when a release is in progress and a scheduled modification which will automatically isolate a liquid release if dilution flow rate becomes inadequat (Closed) Open Item (454/85051-01; 455/85037-01): Commitment to review and revise, as necessary, Byron Chemistry Procedure BCP 400-T47 to preclude potential problems associated with over conservatism in certain calcula-tions (regarding gaseous effluent release dose limits) and possible l non-conservatism in other calculations (regarding release flow rates from special planned gaseous releases such as WGDT and containment purges and l vents). Procedure BCP 400-T47 was revised (Revision 4) on January 14 '

1986. The revised procedure contains modified calculations which eliminate l the potential problems previously identified with this procedur (0 pen) Open Item (454/85051-02; 455/85037-02): Commitment to evaluate thr cause of occasional readings significantly above background observed on the WGDT effluent line monitor between tank releases. The licensee's evaluation is continuing because initial corrective measures have not been fully successful in eliminating the problem. Improvement of the electrical ground of the instrument has eliminated spiking problems. Procedures have been revised to add a 15 minute flush (following each release) of the effluent line, including the WGDT monitor and its piping and to record the monitor readings after flushing. However, elevated monitor readings still occur.

l The licensee is currently investigating the possibility that the order of isolation valve closures following a release may result in trapping of waste gas under pressure between isolation valves and causes the elevated reading when the downstream valve is opened for testing the monitor isolation function before a new release is made. The licensee's l progress in the evaluation of this problem will be reviewed during a l future inspection.

l Unit 2 Preoperational Systems' Demonstrations and Tests The inspector reviewed licensee actions on the following preoperational l

tests:

l OG 2.55.70 Off Gas i This test, to demonstrate the ability of the hogging vacuum pump to l

deliver rated flow at design head, has been completed and reviewed l by the licensee. (All safety related equipment associated with the Unit 2 offgas system was tested during Unit 1 preoperational testing except the containment ventilation isolation valves which will be tested as a part of the ventilation containment (VC) system preoperational test.) Of the six licensee identified deficiencies which remain open (all of which were verified as beino tracked by

'

i l

l

,

)

.

.

'.

l l the licensee), three appear to be of significance. Deficiency 61435 (scheduled for completion by fuel load) involves the need to calibrate the flow indicatin Deficiency 61438scheduled (g loops for forthe steam jetinair completion ejectors time (SJAE).Hot for Integrated l Functional (IHF) tests) involves replacement of four gauges which read in inches of mercury rather than in inches of water. Two of l these gauges are on SJAE lines 2A and 28 and the other two gauges are on the gland steam condensers. Deficiency 61460 (scheduled for completion by IHF) involves a design modification to install needed drain lines in the loop seals from SJAE offgas discharge lines to control water level in the seals. The licensee has a date of April 28, 1986, as a goal for completion of the latter two ceficiencie b. AB 2.01.60 Boric Acid (Pumps and Tank Level Alarms)

This test, to verify that the boric acid transfer pump 2AB03P will deliver required flow at system pressure and that various level alarms of the boric acid tank 2AB03T operate properly, has been conducted and reviewed by the licensee. The five licensee identified deficiencies which remain open appear to be of potential significance and are being tracked by the licensee. Denciency 61197 (System Deficiency No. 1.60-031) involves a retest of the capability of the Unit 2 boric acid filter to handle the capacity from a simultaneous two-pump operation. Deficiency 61997 (System Deficiency No. 1.60-062)

involves recalibration of two level transmitters both of which were slightly out of specification (in the conservative direction)

at the upper end of the scale. Deficiency 61198 (System Deficiency No. 1.60-032) and Deficiency 61199 (System Deficiency No. 1.60-033)

both involved 2AB03P boric acid pump. The former involves excessive oil leakage through the pump casing shaft oil seals, and the latter involves slightly excessive vibration involving boric acid pump 2AB03P. Corrective measures, including seal replacement, were taken and the pump will be retested. Deficiency 61209 (System Deficiency No. 1.60-034) involved the need to recalibrate a density transmitter (at indicator 2 DIAB 006) for indication of boric acid concentratio They are scheduled for completion by fuel load; four deficiencies are planned to be corrected / closed during a retest expected in late February 1986. The licensee was less certain on the planned completion date for action on the fifth deficiency (61997).

c. AB 2.01.70 Boric Acid (Evaporator)

This test, to verify the control setpoint of the (0B) AB evaporator recycle monitor tank, to verify 0B boron recycle evaporator distillate and concentrate pumphead curves, and to verify the OB boron recycle evaporator will meet distillate processing capacity, has been conducted and reviewed by the licensee. Of the ten licensee identified deficiencies which remain open (all of which are being tracked by the licensee), eight appear to be of potential significance. One of these deficiencies is scheduled to be completed l

)

g. ,

by initial criticality; the remaining seven are scheduled for completion by system release to operation (RTO). Deficiency 60681 involves hydrotesting the system. Deficiency 60972 involves insulating the evaporator (in progress). Deficiency 61074 involves installation and functional testing of a new thermal cutout switch (activates at about 280 vs. 200 degrees Fahrenheit) on concentrates pump AB02DB-B. Deficiency 61081 involves a modification on a solenoid valve (in an air line) which will close on receipt of a high pressure signal from the evaporator. It is now ready for component demonstration. Deficiency 61082 involves a modification on the evaporator temperature interlock associated with the rupture dis Construction and calibration are complete and the licensee is now ready to write the startup and component demonstration procedur Deficiencies 61138 and 61139 involve valves 0AB53078 and 0AB5316B respectively, which leaked past seat and disc. Both have been repaired and are ready for required functional check. Deficiency 61203 involves a required modification to reference leg fill line for evaporator level transmitter. This deficiency is scheduled to be completed by initial criticality; however, the modification is now complete and ready for retestin According to licensee personnel, the process monitor system demonstrations and tests will likely begin in late February or early Marc Items to be completed in this area include preoperational testing and demonstration of some systems; post-test evaluations of some systems; and resolution of deficiencies identified during testing and demonstration of these gaseous and liquid processing and monitoring systems. These tests and demonstrations will be reviewed during a subsequent inspectio (0 pen Item 50-455/86005-01)

4. Open Items Open items are matters which have been discussed with the licensee, which will 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 Paragraph . Exit Interview The inspector summarized the scope and findings of the inspection with licensee representatives (Section 1) at the conclusion of the inspection on February 6, 1986. The inspector discussed the likely infonnational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify such documents or processes as proprietar