ML20246F256
| ML20246F256 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/07/1989 |
| From: | Silver H Office of Nuclear Reactor Regulation |
| To: | Wilgus W FLORIDA POWER CORP. |
| References | |
| GL-88-17, TAC-69738, NUDOCS 8907130184 | |
| Download: ML20246F256 (4) | |
Text
w 1
4 1,.
' July 7, 1989 Docket No.150-302' DISTRIBUTION
'" Docket; File;i.f
'NRC & LPDRs PD22 Rdg File b.
- Mr. W., S. Wilgus..
S. Varga, 14/E/3 Vice President, Nuclear Operations G. Lainas, 14/H/4
" Florida Power Corporation G. Wunder D. Miller ATTN: Manager, Nuclear Operations Licensing
. H. Silver P. O. Box 219-NA-21 OGC Crystal River, Florida 32629 E. Jordan, MNBB-3302 B. Grimes, 9/A/2
Dear Mr. Wilgus:
ACRS(10)
H. Sinkule, 'RII
SUBJECT:
CRYSTAL RIVER UNIT.3 - RESPONSE TO GENERIC LETTER 88-17 ON LOSS OF DECAY HEAT REMOVAL WITH RESPECT TO EXPEDITIOUS ACTIONS (TAC NO. 69738)~
On January 4,1989, Flor'ida Power Corporation submitted a response to Generic Letter 88-17 for expeditious, actions to.be taken in the event of a loss of decay heat removal. This response included an attachment that explained your programed enhanceraents.
The. staff has reviewed your response-and finds that it meets the intent of Generic Letter 68-17 with respect to expeditious actions.
Your response was brief, hovever, and therefore did not cover all areas in. detail.
The staf f intends to' conduct an audit of both your response to expeditious.
actions and your programed enhancement program.- The areas where we do not fully understand your resaonses, as indicated in the enclosed comments,' may be covered in the audit of tie expeditious actions.
Sincerely, Original signed by George Wunder FOR Harley Silver, Project Manager Project Directorate 11-2 Division of Reactor Projects-1/II Office.of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ enclosure:
See next page OFoi
[RESPONSETOGL'88-17/CP-3be
[g 3
r er/ d /4 11v Og?gj/89 07/cr/89 07/7 /89 89
/
8907130184 890707 r
PDR ADOCK 05000302 1l P
FDC
O
\\
Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:
Mr. A. H. Stephens State Planning and Development General Counsel Clearinghouse Florida Power Corporation Office of Planning and Budget MAC - A50 Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Flurida 33733 Tallahassee, Florida 32301 Mr. P. F. McKee, Director Chairman Nuclear Plant Operations Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219-NA-2C 110 North Apopka Avenue 4
Crystal River, Florida 32629 Inverness, Florica 32650
)
Mr. Pobert B. Borsum Mr. Rolf C. Widell, Director Babcock & W11cox Nuclear Operations Site Support Nuclear Power Generation Division Florida Power Corporation 1700 Fockville Pike, Suite 525 P.O. Box 219-NA-21 Rockville, Maryland 20852 Crystal River, Florida 32629 Resident Inspector Mr. Gary L. Boldt U.S. Nuclear Regulatory Comission Vice President, Nuclear Production 15760 West Powerline Street Florica Power Corporation Crystal River, Florida 32629 P. O. Box 219-SA-2C Crystal River, Florida 32629 Regional Administrator, Pegion II U.S. Nuclear Regulatory Comission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Jacob Daniel Nash Office of Radiation Contml Departirent of Health ar.d Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 l
Administrator
)
Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General j
Department of Legal Affairs i
The Capitol Tallahassee, Florida 3'.304
F t
,/
Enclosure NRC STAFF OBSERVATIONS ON FLORIDA POWER CORPORATION'S RESPONSE TO GENERIC LETTER 88-17 CRYSTAL RIVER UNIT 3 The NRC staff has reviewed your January 4,1989 response to Generic Letter 88-17.
We find that your response meets the intent of the Generic Letter with respect to expeditious actions. However, your response to some of the items is brief and therefore does not provide the detail to allow us to fully understand some of your actions taken in response to GL 68-17. We have provided the following comments as guidance to assure that your actions are adequate.
1.
You indicate tht administrative procedures are in place to address l
containment closure requirements and that you are participating in a B&W l
Owners Group effort to perform analyses pertinent to lowered loop operation.
L You have not presented any times for closure in the meantime.
Generic Letter 88-17 states that " containment penetrations including the equipment hatch, may remain open provided closure is reasonably certain within ~
2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of initial loss of DHR."
2.
Your response with respect to containment closure is cursory and no information is provided regarding how you will keep track of and control the many potential openings which may have to be closed simultaneously.
l We assume your procedures and administrative controls will address this topic.
3.
You mention that a minimum of two incore thermocouple will be' monitored in the control room whenever the core is in mid-loop condition and the reactor vessel head is on the reactor vessel.
It was not specifically stated whether the temperature indications would be periodically checked and recorded or automatically and continuously monitored and alarmed as recommended in Generic Letter 88-17.
4.
You indicate that you have partially completed installation of a means of pCS level indication which will have indication in the control room and has capability now for limited situations (reactor vessel head off).
You also stated that an evaluation is underway for a secor.d means for RCS level indication. When two instruments are in place, care should be taken to resolve any discrepancy between the two measurement systems. Also, the pressure of the reference leg should approximate the pressure of the void in the hot leg or be compensated to obtain the correct level value.
You have not stated what type the leva:1 measurement systems are, or if they will have alarms.
If they will not have alarms the indications will need to be periodically checked and recorded by operators.
You also indicate that only one method of level measurement is currently available.
This is acceptable in the short term; however, for the longer term, at least two independent level indications must be provided in the control room.
e.
i'--
.2-5.
You have not identified the use of any vent opening on the hot side of the RCS to relieve RCS pressure.
There is no need to respond to the above., observations.
As you are aware, the expeditious actions you have briefly described are an interim measure to achieve an imediate reduction in risk associated with reduced inventory operation, and these will be supplemented and in some cases replaced by programed enhancements.
Please be reminded that we intend to audit both your response to the expeditious actions and your programmed enhancement program.
_ _ _ _ _ _ - _ _ - _ - _ _ _ _ _ _ _ _.