ML20215G645

Notice of Violation from Insp on 860707-11,22-24 & 0922-23

ML20215G645
Person / Time
Site:	LaSalle
Issue date:	10/14/1986
From:	Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20215G639	List: IR 05000373/1986029 ML20215G637 ML20215G645
References
50-373-86-29, 50-374-86-30, NUDOCS 8610210045
Download: ML20215G645 (2)

Text

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NOTICE OF VIOLATION Commonwealth Edison Company Docket Nos. 50-373; 50-374 As a result of the inspection conducted on July 7-11, 22-24, and September 22-23, 1986, and in accordance with the " General Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the following violations were identified:

1. LaSalle Technical Specification 4.0.5 states that inservice testing of pumps and valves be performed in accordance with Section XI of the ASME Code unless specific relief has been granted by the Commission. IWP-3400 of Section XI specifies that inservice testing shall be performed on each pump in the inservice testing program on a quarterly basis during normal operation. Subsection IWP-3230 states in part that for pumps whose test data fall into the alert range, the frequency of testing shall be doubled until the cause of the deviation is determined and the condition corrected.

Contrary to the above, test data taken for the Unit 2 RCIC pump on December 23, 1985, placed the pump into the alert range and as of July 24, 1986, increased frequency testing of the pump had not been conducted.

This is a Severity Level IV violation. (Supplement 1)

2. LaSalle Technical Specification 6.2.A.7 for both Units 1 and 2, requires the licensee to adhere to detailed written procedures for surveillance and testing requirements.

a. Licensee procedure LOS-RI-Q3, " Reactor Core Isolation Cooling System Pump Operability and Inservice Test," requires the use of control room pressure instrument PI-2E51-R604 to measure the Unit 2 RCIC water leg pump discharge pressure.

Contrary to the above, on March 26, 1986, the licensee obtained pressure data from gauge PI-2E51-R501. As a result the licensee unknowingly entered into a Limiting Condition for Operation,

b. Work request number L55974 addressing maintenance performed on the Unit 2 RCIC water leg pump required that the pump be returned to service by performing pertinent portions of procedure LOS-RI-Q3,

" Reactor Core Isolation Cooling System Pump Operability ar.c Inservice Test." Steps F.2 and F.5.d require the collection of vibration velocity date.

Contrary to the above, the licensee failed to obtain vibration velocity data as required on the Unit 2 RCIC water leg pump on March 21 and 26, 1986.

8610210045 861014 PDR ADOCK 05000373 G PDR

Notice of Violation 2

c. Step F.3.c of licensee procedure LOS-RH-Q1, "RHR and RHR SW Pump Inservice Test for Operational Conditions 1, 2, 3, 4 and 5,"

specifies that pressure instrument PI-1E12-R002C be used for obtaining Unit 1 LPCI water leg pump suction pressure. Steps F.7, F.8, and F.9 of LOS-RH-Q1 specify that pressure gauge PI-1E12-P612C be used for obtaining the "C" LPCI pump discharge pressure.

Contrary to the above, on March 9, 1986, the licensee obtained pressures for the Unit 1 LPCI and LPCI water leg pumps test data using instruments other than those identified in LOS-RH-Q1.

This is a Severity Level IV violation. (Supplement 1)

3. La Salle Technical Specification 4.0.5 states that inservice testing of pumps and valves be performed in accordance with Section XI of the ASME

. Code unless specific relief has been granted by the Commission. IWP-3111' states that those pumps not tested during shutdown periods shall be tested and their characteristic parameters verified to be within the acceptable ranges as defined in the inservice testing program within one week of return to service. The licensee drained the reactor cavity on Unit 1 down on May 10, 1986, thereby returning the suppression pool to normal conditions and requiring two ECCS pumps to be operable.

Contrary to the above, the licensee did not verify the characteristic parameters of the two ECCS pumps declared operable to be within the acceptable range.as defined in the inservice testing program within one week of their return to service in that the "B" and "C" RHR pumps were tested on June 17 and May 23, 1986, respectively, and had not been acceptably tested during the shutdown period.

This is a Severity Level IV violation. (Supplement 1)

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 violation: (1)correctiveaction taken and the results achieved; (2) corrective action to be taken to avoid further violation; and (3) the date when full compliance will be achieved.

Consideration may be given to extending your response time for good cause shown.

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