ML19330A489
| ML19330A489 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/23/1980 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| 3--3-A-3, 3-0-3-A-3, NUDOCS 8007280373 | |
| Download: ML19330A489 (6) | |
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M Power COR PO R A T eO N July 23, 1980 File:
3-0-3-a-3 Mr. Robert W. Reid Chief Operating Reactors Branch #4 U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 FIRE PROTECTION PROGRAM MODIFICATIONS
Dear Mr. Reid:
This letter provides an up-to-date status of our Fire Protection Modifica-tions identified in the Safety Evaluation Reoort transmitted ta us on July 27, 1979.
In our letter of June 11, 1980, we stated that our responses to the items of SER were made between December 6,1979, nd January 15, 1980, and the ninety-day responses from the NRC were due beginning March 6,1980.
- Also, we stated that due to the delay in responding to our submittals it will not be possible to have all the modifications completed at CR-3 by Oct-ober 1980.
To date, we have not received any responses from the NRC con-cerning our submittals.
The attached tables provide an up-to-date status of each item of the SER.
We have completed all the modifications required by items included in Table 1..
For itens in Table 2, we he.ve completed the design and issued construction work packages to the CR-3 site.
All items except 3.5 are expected to be completed by October l'80.
Item 3.5 is 15% complete and re-quires installation of containment isolation valves, which are expected to be delivered in September 1981.
This will require about 30 days of access into the Reactor Building and will be completed during the subsequent re-fueling outage.
Even though we have not recein _ the NRC's responses to our submittals on Items 3.2 and 3.5, we have proceeded with the modifica-tions because of the low cost-to-risk afforded by these modifications, and with the confiderce that our modifications meet the intent of the SER and will be acceptable to the NRC.
8007280 3 )
General Office 3201 Tnirty-founn street soum. P O Box 14042. St Petersbu g Flor:da 33733 e 813-866-5151
Mr. Robert. W. Reid Page Two July 23, 1980 Table 3 contains items requiring NRC's responses to our submittals as de-lineated in the SER, prior to initiating any construction work packages, lead times required to complete modifications and priority for modifica-tions as it applies to safety.
Item 3.1, the safe shutdown panel, requires a plant refueling outage.
Because of safety considerations and lead time requi red for _ installation, highest priority has been assigned to this item. We request an expeditious review by the NRC of our submittals on a priority basis by taking into consideration the lead time involved in each modi fication.
Should you require any additional information, or wish to discuss our sub-mittals, please contact us.
The technical contact is Mr. Walt G. Lobo at (813) 866-4422.
Very truly yours, FLORIDA POWER CORPORATION
$yG P. Y. Baynard Manager Nuclear Support Services Lobo (FireProt)DN97-2 Attachments i
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STATE OF FLORIDA COUNTY OF PINELLAS-P. Y. Baynard states -that she is the Manager, Nuclear Support Services Department of Florida Power Corporation; that she is authorized on the part of said company to sign and file with the Nuclear Regulatory Com-mission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of her knowledge, infonnation and belief.
Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 23rd day of July,1980.
Wpftc(
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Notary Public o
Notary Public, State of Florida at Large, My Commission Expires: May 29. 1984 PYB/MACNotary(DN-98)
TABLE 1 STATUS OF FIRE PROTECTION MODIFICATIONS MODIFICATIONS ALREADY COMPLETED SER ITEM MODIFICATION COMPLETION DATE NRC APPROVAL DATE PRIORITY FOR REVIEW / MODIFICATION
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3.3 3.4 All these modifications NRC approved Not applicable 3.9 are completed as of these in the since already July 1, 1980.
SER.
installed.
3.11 3.13 3.16 3.19 i
3.21.1 3.21.3 3.22 3.24 Legend:
Priorities are based upon lead time for all items, except for Item 3.1; priority for Item 3.1 is based upon both lead time and safety consid-erations.
Highest Priority - 1 Higher Priority
-2 i
High Priority
-3 Low Priority
-4 Lobo (FireProt)DN97-2 l
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TABLE 2 STATUS OF FIRE PROTECTION MODIFICATIONS MODIFICATIONS FOR WHICH DESIGN IS COMPLETED AND CONSTRUCTION WORK PACKGAGE ISSUED SER ITEM FPC RESPONSE TO NRC NRC RESPONSE DUE PROJECTED DATE PRIORITY FOR TO FPC 0F IN5iALLATION RE'!!EW/ MODIFICATION i
3.2 12-6-79 3-6-80 9-30-80 4
3.5*
1-8-80 4-8-80 Requires plant 3
shutdown and 30 days access to the Reactor Building 3.7 3.8 3.10 NRC approved NRC approved 9-30-80 3.12 these items in these items in Not the SER the SER Applicable 3.20 1
3.21.2 3.24
- This modification is approximately 15% complete.
Delivery of containment isolation valve is expected in 9/81.
This modification will require plant shutdown and approximately 30 days access into the Reactor Building, and will be completed in the subsequent refueling i
outage.
Therefore, the priority is high.
Lobo (FireProt)DN97-2
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TABLE 3 STATUS OF FIRE PROTECTION MODIFICATIONS ITEMS REQUIRING NRC'S APPROVAL PRIOR TO INITIATING CONSTRUCTION WORK PACKAGE SER ITEM FPC RESPONSE TO NRC NRC RESPONSE DUE LEAD TIME REQ'D FOR PRIORITY FOR SUBMITTED ON TO FPC INSTALLATION AFTER REVIEW / MODIFICATION NRC'S APPROVAL 3.1*
12-17-79 3-17-80 12 months **
1 3.6 12-6-79 3-6-80 6 months 3
3.14 1-15-80 4-15-80 4 months 3.15 12-6-79 3-6-80 7 months 2
3.17 12-6-79 3-6-80 1 month 4
1.18 12-6-79 3-6-80 7 months 3
3.23 12-6-79 3-6-80 None 4
3.25 12-6-79 3-6-80 6 months 2
3.27 12-6-79 3-6-80 6 months 3
3.28 12-6-79 3-6-80 6 months 3
3.29 12-6-79 3-6-80 7 months 2
3.30 12-6-79 3-6-80 6 months 3
3.31 12-6-79 3-6-80 None 4
- This item reflects safe shutdown panel only. Fire Protection modifications identified in 3.1 are included in other items.
- This modification requires a plant refueling outage.
Lobo (FireProt)DN97-2