ML20249C213

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Summarizes NRC Predecisional Enforcement Conference Held on 980618 Re Apparent Violations at Quad Cities Nuclear Power Station,Units 1 & 2 Involving 10CFR50.48, Fire Protection & 10CFR50.59, Changes,Tests & Experiments
ML20249C213
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 06/23/1998
From: Grobe J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Kingsley O
COMMONWEALTH EDISON CO.
References
EA-98-175, EA-98-231, NUDOCS 9806260200
Download: ML20249C213 (45)
v • d • e


Text

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June 23, 1998 EA Nos.98-175; 98-231 Mr. Oliver D. Kingsley President, Nuclear Generation Group Commonwealth Edison Company ATTN: Regulatory Services Executive Towers West til 1400 Opus Place, Suite 500 Downers Grove,IL 60515

SUBJECT:

NRC PREDECISIONAL ENFORCEMENT CONFERENCE

SUMMARY

Dear Mr. Kingsley:

This refers to the Predecisional Enforcement Conference conducted by Mr. Carl Paperiello, Acting Regional Administrator, other members of the Region 111 staff, and Headquarters staff in the Region til office, on June 18,1998. The subject of this conference was the apparent violations at the Quad Cities Nuclear Power Station, Units 1 and 2, identified in NRC letter dated May 15,1998 (50-254/97023(DRS); 50-265-97023(DRS)) involving 10 CFR 50.48,

  • Fire Protection" and 10 CFR 50.59, " Changes, Tests and Experiments."

During the conference, your staff acknowledged the violations and presented information addressing the background, conclusions, significance, and lessons leamed for each area. The first area involved inadequacies in post-fire safe shutdown capabilities for certain fire areas containing safe shutdown equipment, such that safe shutdown conditions may not be achieved and maintained if a postulated fire occurred. The second area involved a change in the safe shutdown procedures as described in the safety analysis report which involved an unreviewed i safety question without prior Commission approval. Copies of the NRC's and licensee's handouts, and the attendance list are enclosed with this summary.

You will be notified by separate correspondence of our decision regarding the enforcement action based on the information presented and discussed at the Predecisional Enforcement Conference. No response is required until you are notified of the proposed Enforcement Action.

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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practices," a copy of this letter and its enclosures will be placed in the NRC Public Document Room.

Sincerely, Original.~/s/ J. A. Grobe John A. Grobe, Director - .

I Division of Reactor Safety Docket Nos.: 50-254; 50-265 '

License Nos.: DPR-29; DPR-30

Enclosures:

As stated )

cc w/encis: M.Wallace, Senior Vice President D. Helwig, Senior Vice President G. Stanley, PWR Vice President J. Perry, BWR Vice President D. Ferrar, Regulatory Services Manager

1. Johnson, Liceasing Director DCD - Licensing J. Dimmette, Jr., Site Vice President W. Pearce, Quad Cities Station Manager C. Peterson, Regulatory Affairs Manager R. Hubbard N. Schloss, Economist Office of the Attorney General State Liaison Officer Chairman, Illinois Commerce FAmmission W. Leech, Manager of Nuclear MidAmerican Energy Company DOCUMENT NAME: G:DRS\qua06228.drs

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OFFICE Rlli lC- Rill 16 Rlli lE Rill _#l Rill 2l NAME Chyu:sd K Gardner P Rini htT1- Clayton #4- G6lpiV DATE 06M/98 069/98 06AA/98 06/12/98 06/ 9 98 OmCIAL RECORD COPY m

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O. Kingsley - Distnbution:

J. Goldberg, OGC w/encls J. Lieberman, OE w/encls B. Boger, NRR w/encls SAR (E-Mail)

Project Mgr., NRR w/encls C. Paperiello, Rlil w/encis i

J. Caldwell, Rlli w/encls i B. Clayton, Rlli w/encis SRI Quad Cities w/encls

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Attendance List -

NRC Predecisional Enforcement Conference June 18,1998 LiceRHtt D. Sager Vice President - Generation Support, Comed R. Krich Vice President - Regulatory Services D. Helwig ' Senior Vice President J. Dimmette, Jr. Site Vice President, Quad Cities L Pearce Station Manager B. Holbrook Engineering Manager S. Darin Engineering C. Peterson Regulatory Assurance J, Brownell Fire Protection Engineer NEG C. Paperiello Acting Regional Administrator, Region ill J. Caldwell Deputy Regional Administrator J. Grobe Director, Division of Reactor Safety M. Dapas Deputy Director, Division of Reactor Project M. Ring . Chief, Reactor Project Branch 1 R. Gardner Chief, Engineering Specialists Branch 2 H. Clayton Enforcement Officer V.Lougheed Reactor Engineer D. Chyu Reactor Engineer C. Miller Senior Resident inspection, Quad Cities S. West Chief, Fire Protection Engineering Branch, NRR B. Pulsifer Project Manager, NRR 1

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TWO APPARENT VIOLATIONS IDENTIFIED

  • FROM DECEMBER 1982 TO SEPTEMBER 1997, THERE EXISTED INADEQUACIES IN SAFE SHUTDOWN CAPABILITIES FOR CERTAIN FIRE AREAS CONTAINING L tFE SHUTDOWN EQUIPMENT, SUCH THAT SAFE SHUTDOWN CONDITIONS MAY NOT BE ACHIEVED AND MAINTAINED IF A POSTULATED FIRE OCCURRED.

e IN DECEMBER 1997, THE LICENSEE MADE A CHANGE IN PROCEDURES AS DESCRIBED IN THE SAFETY ANALYSIS REPORT WHICH INVOLVED AN UNREVIEWED SAFETY QUESTION WITHOUT OBTAINING PRIOR COMMISSION APPROVAL.

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i INADEQUACIES IN SAFE SHUTDOWN CAPABILITIES 10 CFR 50, APPENDIX R, SECTION J, REQUIRES THAT EMERGENCY LIGHTING UNITS BE PROVIDED IN ACCESS AND EGRESS ROUTES AND ALL AREAS NEEDED FOR OPERATION OF SAFE SHUTDOWN EQUIPMENT.

10 CFR 50, APPENDIX R, SECTION lli.G, REQUIRES THAT ALTERNATIVE OR DEDICATED SHUTDOWN CAPABILITY BE PROVIDED WHERE SEPARATION REQUIREMENTS ARE NOT MET. MANY AREAS AT THE QUAD CITIES FACILITY j REQUIRE ALTERNATE OR DEDICATED SHUTDOWN CAPABILITY.

1 10 CFR 50, APPENDIX R, SECTION lli.L SPECIFIED THE {

PERFORMANCE EXPECTATION FOR ALTERNATIVE OR DEDICATED SHUTDOWN CAPABILITY TO INCLUDE THE ABILITY TO (A) ACHIEVE AND MAINTAIN SUBCRITICAL REACTIVITY CONDITIONS IN THE REACTOR; (B) MAINTAIN REACTOR COOLANT INVENTORY; (C) ACHIEVE AND MAINTAIN HOT SHUTDOWN CONDITIONS; (D) ACHIEVE COLD SHUTDOWN CONDITIONS WITHIN 72 HOURS; AND (E)

MAINTAIN COLD SHUTDOWN CONDITIONS THEREAFTER.

l "EEc2 Esu"o*E#S*"SIMS"ESTE EuSIEE'YS"le'EZEfo'u" *"" "

INADEQUACIES IN SAFE SHUTDOWN CAPABILITIES A POSTULATED FIFE OCCURRING IN ANY AREA COVERED BY 14 SEPARATE SAFE SHUTDOWN PATHS COULD RENDER SAFE SHUTDOWN EQUIPMENT INOPERABLE TO THE EXTENT THAT SAFE SHUTDOWN CONDITIONS WOULD NOT BE ACHIEVED AND MAINTAINED. FOR EXAMPLE:

1. CENTRAL TURBINE BUILD;NG AREA l (PATH H FOR UNIT 2)

RCIC SYSTEM COULD BE INOPERABLE TO MAINTAIN REACTOR COOLANT INVENTORY RHR 19 A OR B VALVES COULD BE RENDERED INOPERABLE DUE TO HOT SHORT DAMAGE.

THESE VALVES ARE NEEDED TO INITIATE TORUS WATER REJECT IN PREPARATION FOR ADS )

OPERATION  !

RECIRCULATION 5 VALVE MIGHT NOT CLOSE DUE TO HOT SHORT DAMAGE; THEREFORE, SHUTDOWN COOLING COULD NOT BE INITIATED IM$7fa^"'c7es $o"su"!SE ES*'UM"e'afo"'ESTO #eiu'ES$75a"c5EM"Efo"n^"" ** "

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INADEQUACIES IN SAFE SHUTDOWN CAPABILITIES

2. UNIT 1 TUr'alNi BUILDING (PATH D3)

MSL OLN VALVES FOR HIGH/ LOW PRESSURE INTERFACE COULD BE INOPERABLE OPERATORS COULD NOT GAIN ACCESS TO THE HPCI 8 VALVE SUCH THAT THE SSMP COULD NOT MAINTAIN REACTOR INVENTORY

- RHR 19 A & B VALVES, RECIRCULATION 5 VALVE, l AND RHR PUMP COULD BE INOPERABLE SAFE SHUTDOWN PROCEDURE CONTAINED MISINFORMATION FOR LIFTING AND LANDING ADS LEADS RHRSW AND CCST INDICATIONS MIGHT NOT BE AVAILABLE TO OPERATORS RTHER FkE A D SU T TO C GE PRIOR TO AN RE ULT NG N ORCEME ACTION  !

INADEQUACIES IN SAFE SHUTDOWN CAPABILITIES

3. CONTROL ROOM, AUXILIARY ELECTRIC ROOM, CABLE SPREADING ROOM AND COMPUTER ROOM (PATH E22 FOR UNIT 1)

MSL DRAIN VALVES FOR HIGH/ LOW PRESSURE INTERFACE AND THE RCIC PUMP COULD BE INOPERABLE TO MAINTAIN REACTOR INVENTORY

- RHR 19 A&B VALVES, RECIRCULATION 5 VALVE, AND RHR PUMP COULD BE INOPERABLE SAFE SHUTDOWN PROCEDURE CONTAINED MISINFORMATION FOR LIFTING AND LANDING ADS LEADS ONE EXAMPLE WAS IDENTIFIED WHERE THE LICENSEE FAILED TO PROVIDE ADEQUATE LIGHTING IN THE UNITS 1 AND 2 HPCI ROOMS AND 1B AND 2B RHR ROOMS.

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l UNTIMELY AND INADEQUATE SAFETY EVALUATION 10 CFR 50.59 ALLOWS THE LICENSEE TO MAKE CHANGES IN THE FACILITY AS DESCRIBED IN THE SAFETY ANALYSIS REPORT AND MAKE CHANGES IN THE PROCEDURES AS DESCRIBED IN THE SAFETY ANALYSIS REPORT WITHOUT NRC APPROVAL PROVIDED THE CHANGE DOES NOT INVOLVE AN UNREVIEWED SAFETY QUESTION.

1 A PROPOSED CHANGE INVOLVES AN UNREVIEWED SAFETY QUESTION IF A POSSIBILITY FOR AN ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE THAN ANY EVALUATED PREVIOUSLY IN THE SAFETY ANALYSIS REPORT MAY BE CREATED.

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I THER REVIE D SU TTO N E PRIOR TO R S .T NG N CEME ACTION

UNTIMELY AND INADEQUATE SAFETY EVALUATION

  • ON DECEMBER 2,1997, THE LICENSEE FAILED TO

-PERFORM A SAFETY EVALUATION FOR THE USE OF THE STATION BLACKOUT DIESELS IN THE REVISED SAFE SHUTDOWN PROCEDURES. )

e THIS SAFETY EVALUATION WAS NOY PERFORMED UNTIL PROMPTED BY THE NRC DURING AN ONSITE MANAGEMENT MEETING ON DECEMBER 16,1997.

e ON DECEMBER 18,1997, THE LICENSEE PERFORMED A SAFETY EVALUATION WHICH WAS INADEQUATE IN THAT IT DID NOT FULLY EVALUATE THE MANUAL ACTIONS REQUIRED TO SUPPORT OPERATIONS OF THE SBO DG.

  • IN MARCH 1998, THE LICENSEE DETERMINED THAT i THESE MANUAL ACTIONS INVOLVE AN UNREVIEWED SAFETY QUESTION.

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