IR 05000295/1980007
| ML19310A750 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 05/12/1980 |
| From: | Kohler J, Little W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19310A742 | List: |
| References | |
| 50-295-80-07, 50-295-80-7, 50-304-80-06, 50-304-80-6, NUDOCS 8006230077 | |
| Download: ML19310A750 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-295/80-07; 50-304/80-06 Docket No. 05000295; 0500G304 License No. DPR-39; DPR-48 Licensee:
Conunonwealth Edison Company Post Office Box 767
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60690 Chicago, IL
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Facility Name: Zion Nuclear Power Station, Units 1 and 2 Inspection At: Zion site, Zion IL Inspection Conducted-A ril 14-33, 1980 aA
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Inspector:.
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Approved By:
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Reactor Pr jects Section 1-2
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Inspection Summary Inspection on April 14-30, 1980 (Report No. 50-295/80-07; 50-304/80-06)
Areas In:pected: Announ:ed inspection by the Resident Inspector of cer-tain licensee actions taken,to comply with the Confirmatory Order issued February 29, 1980. The insp'ection involved 20 inspector-hours on site by one NRC inspector.
Results: No items of noncompliance were identified.
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DETAILS 1.
Persons Contacted
- N. Wandke, Station Superintendent
- L. Soth, Operating Assistant Superintendent T. Reick, Technical Staff Engineer F. Lentine, Technical Staff Engineer
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K. Ainger, Technical Staff Engineer A. Krawczak, Technical Staff Engineer K. Madden, Technical Staff Engineer C. Schultz, Training Supervisor B. Lowe, Training Instructor
J. Gilmore, Unit 2 Operating Engineer
- Denotes those present at the exit meeting.
2.
Review and Verification of Interium Measures References:
(1)
NRC Confirmatory Order of February 29, 1980 (2)
Commonwealth Edison Co. letter to H. Denton, 3/28/80 (serial 2636A)
(3)
Commonwealth Edison Co. letter to H. Denton, 3/28/80 (serial 2661A)
a.
Background On February 29, 1980, a Confirmatory Order was issued by the Commission for Zion Units 1 and 2 amending facility operating licenses to incorporate certain commitments made by Common-wealth Edison. Commonwealth Edison made these additional commitments in response to the Commission's desire to provide additional safety measures at Zion Station because of the high population surrounding the site.
b.
Compliance with Confirmatory Order The following items have been reviewed for compliance w *th the Or der by the resident inspector in accordance with instruction provided by the Office of Insnection and Enforcement.
(1)
(Item A.1) Maintain reactor power level as necessary such that calculated fuel peak clad temperature does not exceed 2050*F under large break LOCA conditions per 10 CFR 50, Appendix K analysis submitted on October 22, 1979.
The licensee's September 29, 1979, Appendix K analysis indicates that an Fq=2.20 results in a peak clad tempera-ture of 2048'F. Since the currently authorized Fq limit-2-
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by technical specification is 1.93, the licensee is in compliance and this item is closed.
(2)
(Item A.2) Revise plant operating procedures as necessary to require a base load mode of operation only, without load follow except for power reductions required to main-tain system load for grid stability, required for main-tenance, or as required by Technical Specifications.
The inspector reviewed " Load Dispatcher Directive", F. Palmer to Load Dispatcher dated March 10, 1980, which incorporates the requirement of item A.2.
The licensee is in ecmpliance and this item is closed.
(3)
(Item A.3) Conduct a low pressure gross leak test of con-tainment prior to any start up from cold shutdown condi-tions as indicated in Annex 1.
If other means can be found to verify containment integrity, the licensee may propose such procedures to the Commission for its review and approval.
The low pressure gross leak test has not been performed since Unit 1 and 2 have operated at power since issuance of the Confirmatory Order. Earliest scheduled date for performance of this test will be during the Unit 2 refuel-ing outage scheduled to begin on May 2, 1980.
This item will be inspected at a later date and is de-signated unresolved item 295/80-07-01.
(4)
(Item A.4) Maintain at least two senior reactor operators (SR0s), one of whom may be the shift supervisor, in the control room at all times during power operations or hot shutdown, except that the shift supervisor shall be allowed to leave the immediate vicinity of the control room as duties may require, provided he is available to respond to an emergency by returning to the control room within ten minutes. The shift or watch supervisor's office is con-sidered part of the control room.
The licensee procedure ZAP l-51-1, " Station Organization" impliments the above requirements. The inspector confirmed that these requirements are met and this item is considered closed.
(5)
(Item A.5) Conduct testing to assure that LPI/RHR check valves are in fact installed correctly and functioning as pressure isolation barriers when the plant is at pressure and producing power. ' Verification of valve operability-3-L
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O shall be performed prior to plant restart if shutdown at
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the time of issuance of the Order and thereafter whenever RCS pressure has decreased to within 100 psig of RHR system
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design pressure.
Both Units.1 and 2 have not had system pressure decrease to within 100 psig of the RHR system. The earliest-anticipated date for performancesof this test will be
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during the Unit 2 refueling outake beginning May 2, 1980.
The inspector has reviewed the ECCS to verify that all re-quired check valves will be listed. According to the ECCS
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review the following check valves will require periodic leak testing at a frequency of at least every refueling outage.
i LOOP (TRAIN)
CHECK VALVE-P & ID A B C D RH 8736 x x RH 8949 x x SI 9001 M 65 x x x x SI 9012 M 64 x x x x SI 9002 M 65 x x x x SI 8957 M 65 x x The results of the ECCS check valve leak test will be reported at a later date and is designated unresolved item 295/80-07-02.
(7)
(Item A.7) Require that all reactor operators and senior reactor operators conduct simulator training and in plant walk-through of the following emergency procedures. Due to the licensee's large operating staff the in plant walk
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-throughs shall be completed prior to the next reactor startup following issuance of the Order, or within sixty
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days of the date of issuance, whichever occurs first.
Those reactor operators and senior reactor operators who have not received simulator training within the past four months on these items shall be given such simulator train-ing within 90 days of the date of the Order:
a.
Plant or reactor startups to include a range wherein reactivity feedback from nuclear heat addition is noticeable and heatup rate is established.
b.
Manual control of steam generator level and/or feed-
. water during startup and shutdown.
c.
Any significant (10%) power change using manual rod control.
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d.
Loss of Coolant.
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(i)
including significant PWR steam generator leaks (ii) inside and outside containment (iii) large and small, including leak rate determination (iv) saturated reactor coolant response (PWR)
e.
Loss of core coolant flow / natural circulation f.
Loss of all feedwater (normal and emergency)
g.
Station blackout h.
Anticipated Transients Without Scram (ATWS)
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Stuck open relief valve on secondary side J.
Intersystem LOCA The inspector reviewed the training department records and
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determined that all licensed personnel having shift respon-sibilities have received the required walk-through and simulator training.
The licensee is in compliance and this item is closed.
(8)
(Item B.1) A vendor representative will be stationed on site for engineering consultation at Zion Unit I and Unit 2 on plant operations and maintenance to increase plant safety. The representative shall be from the NSSS vendor, architect / engineering or start up engineering firm.
A vendor representative from the NSSS vendor, Westinghouse Electric Corporation has been stationed on site.
The licensee is in rampliance and this item is closed.
(9)
(Item B.3) Emergency action levels shall be revised to require notification of the NRC for all events in the emergency classes described in NUREG-0610, September 1979.
Commonwealth Edison has issued Standing Orders at Zion Station to meet this requirement.
The licensee is in compliance and this item is closed.
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(10) (Item B.5) Plant personnel shall be trained or retrained in
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the following areas within thirty days, or prior to startup if required by the Lessons Learned implementation schedule Plant personnel shall also be retrained in the following areas within thirty days of the time that there are signifi-cant changes to the procedures or requirements applicable to these areas:
Containment and Degraded Core Sampling Degraded Core - Training Emergency Power for Pressurizer Heaters and Decay Heat Removal Containment Isolation Containment Purge / Purge Valve Operation Subcooling Meter Operation Technical Support Center Onsite Operational Support Center Near-Site Emergency Operations Center Emergency Preparedness Plan In-Plant Area Airborne Radioiodine Monitors The inspector reviewed ZAP 252-1 and 252-2, " Licensed Training Requirements", and the training department re-cords and verified that licensed personnel having shift responsibilities received the required training.
The licensee is in compliance and this item is closed.
(11) (Item B.6) The licensee shall perform diesel generator testing in accordance with Regulatory Guide 1.108 with a corresponding change in the allowable outage time stipul-ated in the Limiting Conditions of Operation as follows:
Number of DG Failures Test Interval (Days)
Allowable In Prior 100 Test (R.G. 1.108)
Outage Time 0 or 1
As Is
14 As Is
7 As Is
3 32 hr.
3 8 hr.
6 or more
None*
- Plant must achieve hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The inspector has reviewed the licensee's compilation of the'last 100 diesel generator surveillance tests performed-6-
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on a unit specific basis and has determined that acceler-ated diesel generator testing has been incorporated into the licensee's procedures.
The licensee is in compliance with this item.
Regulatory Guide 1.108 also requires an 18 month refueling interval surveillance test. The 18 month diesel generator surveillance requirements are presently being incorporated into the Unit 2, 1980 refueling outage scheduled to begin May 3, 1980.
This item will be inspected at a later date and is desig-nated unresolved item 295/80-07-03.
(12) (Item B.7) Requirements regarding reactor operator qual-ifications shall be revised to incorporate the following for applications submitted after June 1,1980 except for training classes in session at time of issuance of this Order:
The following experience shall be required for senior a.
operator applicants:
Applicants for senior operator licensee shall have four years of responsible power plant experience.
Responsible power plant experience shall be that obtained as a control room operator (fossil or nu-clear), field operator (nuclear) or as a power plant staff engineer involved in the day-to-day activities of the facility, commencing with the final year of construction. A maximum of two years' power plant experience may be fulfilled by academic or related technica'l training, on a one-for-one time basis.
Two years shall be nuclear power plant experience.
At least six months of the nuclear power plant ex-perience shall be at the plant for which the appli-cant seeks a license.
b.
The hot training programs shall be modified so that the training concentrates on the responsibilities and functions of the operator, rather than the senior operator. All individuals who satisfactorily complete this hot training program will be allowed to apply for an operator license. At least three months experience as a licensed-operator is necessary before applying for a senior operator license.
The three month continuous on-the-job training fo,r c.
hot operator applicants shall be as an extra person-7-
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on shift in the control room. The hot senior oper-r ator applicants will have three months continuous on-the-job training as an extra person on shift in training.
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d.
- In addition to the presently approved training pro-grams, all replacement applicants shall participate in simulator training programs.
e.
Training center and facility instructors who teach
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' systems, integrated respose, and transient and simu-lator courses shall demonstrate their competence to a
the NRC_by successful completion of an SRO written examination.
Instructors shall be enrolled in appro-priate requalification programs to assure that they are cognizant of current operating history, problems and changes to procedures and administrative limitations.
The inspector reviewed ZAP-1-51-1, " Station Organiza-
tion" and ZAP-252-1 and Zap 252-2, "Licenesed Training
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Requirements", and other training records.
The licensee is in compliance and this item is closed.
(13) (Item B.8) Requirements regarding reactor operator qual-ifications shall be revised such that all operator licensees shall participate in periodic retraining and recertifica-tion on a full scope simulator representative of Zion Units 1 and 2.
The frequency of training will be on an annual basis.
The inspector has reviewed this item and determined that i
the licensee has incorporated this requirement in the licensed training program, ZAP 252-1 and ZAP 252-2.
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The licensee is in compliance and this item is closed.
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(14) (Item C.5) Establish an on-site group whose function shall be to examine plant opecating characteristics, NRC bulletins, Licensing Information Service advisories and other appro-
priate sources which may indicate areas for improving plant safety. Where useful improvements can be achieved, the
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group shall develop and report detailed recommendations for j
revised procedures,: equipment modifications or other in-1provements to ofisite management.
i The inspector reviewed the licensee's procedure ZAP 254-2,
" Zion Plant Nuclear Safety Review Committee" and found that the, licensee has formed a new on-site group to meet the requirements of item C.5 and is in compliance and this item is-closed.
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.(15)'(Items D.1, D.2, E.1) Items with prefix D are 90 day
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compliance items while prefix E are 120 day compliance x
items. These three items will be reviewed by the in-Tspector as they become due beginning May 30, 1980 and June 30, 1980.
The above items are designated unresolved 295/80-07-04.
'3.
Unresolved Items Unresolved items are matters about.which more information is re-quired in order to ascertain whether they are acceptable items, items of noncompliance or deviations.. Unresolved items disclosed during the inspection are discussed in paragraph 2.
4.
Management Exit'
The inspector met with Mr. Wandke at the conclusion of the inspec-tion and summarized the results. No items of noncompliance were id5ntified.
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