ML17342A657
| ML17342A657 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/13/1986 |
| From: | Stello V NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Fascell D HOUSE OF REP. |
| Shared Package | |
| ML17342A658 | List: |
| References | |
| NUDOCS 8608210132 | |
| Download: ML17342A657 (6) | |
Text
r AR 13 II DISTRIBUTION NGrace, RII
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g OGC NRC PDR w/cy of'ncoming SECY Local PDR w/cy of incoming VStello The Honorable Dante B. Fascell EDO. ¹1977 PPAS (EDO¹1977)
United States House of Representatives EDO Reading DMossburg w/cy of inc.
Washington,, D.
C.',
20515-HDenton/RVollmer TNovak/PBaker JTayl or LRubenstein Dear Congressman Fascell:
CRossi DMcDonald w/cy of inc.
PD¹2 Rdg.
DMilier I
am pleased to respond to your July 16, 1986 request in relation to Ms; Joette Lorion of the Center for Nuclear Responsibility who, by letter (Enclosure
- 1) to Mr.. Hugh Thompson, Director, Division of PWR Licensing-A, expressed concern that:
( 1) orida Power and Light Company (FPL) has requested an extension for 'th'e submittal date o
e es r
o he reactor vessel material surveillance
- specimen, capsule' from Turke Point Unit 3 fracture toughness tests; and (2) Unit 3 experience is being use or ns to. determine the integrity of the Unit" 4 reactor vessel.
In relation to Ms. Lorion's second, concern, I have addressed this in detail by my letter to you dated July 29, 1986, in response to your May 29, 1986 request.
I noted that:
(1) the NRC staff reviewed and approved an integrated surveillance program for Turkey Point, Units 3 and 4; (2) provided the basis for the approval; and (3) indicated that test data from many sources is used in assessing reactor vessel embrittlement.
I also noted that 10 CFR 50.61 establishes a screening criterion and acceptable means for calculating the reference temperature to judge the condition of reactor vessels at all sites.
Ms. Lorion's concern relating to FPL's extension request until September 1, 1986, for the submittal of the test results is based on the FPL letter dated April 30, 1986 (Enclosure 2), which indicated that the capsule containing the test specimens was removed in late April 1985.
The NRC staff then requested the exact with-drawal date, which FPL indicated was March 16, 1985.
10 CFR 50, Appendix H, Section III.A specifies that licensee's staff provide a summary report of the analysis of surveillance capsules within one-year after their withdrawal from the reactor.
Therefore, the April 30, 1986, request was not timely and could not be granted.
Subsequently, by the letter dated July ll, 1986 (Enclosure 3),
FPL has requested an exemption pursuant to 10 CFR 50. 12, from the one-year requirement specified in 10 CFR 50, Appendix H, Section III.A.
FPL indicated they will supply the required report to the staff on or before September 1, 1986, which is less than six months from the required date of March 16, 1986.
They further indicated that the capsule analysis and testing is contracted to Southwest
- Research, Inc.
(SWRI).
The requested delay is due to circumstances beyond their control, namely the death of the SWRI Project Manager.
Although FPL has received the SWRI report, they require sufficient time for their technical staff to review and resolve any comments.
The internal review and approval is normal practice in the industry and is necessary since they are responsible for the content and accuracy of.the information documented.,in the report.
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The Honorable Dante B. Fascell j
The purpose of the reactor vessel material surveillance program is to monitor the'ffects of neutron irradiation damage and the thermal environment on the reactor vessel beltline material integrity.
The analysis of the surveillance capsules serves to determine the safety margin of the beltline material associated with the pressure-temperature limits as required by Appendix G of 10 CFR Part 50.
The existing Technical Specifications for the Turkey Point Plant,'nits 3 and 4, include pressure-temperature limits to be effective for the first 10 Effective Full Power Years (EFPY) of operation for both units.
As of Nay 31, 1986, exposure for the Unit 3 reactor vessel is 8.7 EFPY and the present exposure for Unit 4 is 8.31 EFPY.
These present exposures are below the allowable limit,as set forth in the operating licenses, and the summary report of the capsule in question will be submitted well in advance of reaching the licensing limit.
Hence, there is an adequate margin between the actual amount of neutron irradiation exposures to both reactor vessels and the exposure permitted by the operating licenses.
In su@nary, th'ere is no immediate safety concern based on the reactor vessel neutron exposure of each unit, which is well below the allowable limits required by the Turkey Point Plant Technical Specifications.
The staff is currently evaluating FPL's exemption request pursuant to 10 CFR 50. 12.
I would like to note that Ms. Lorion initiated proceedings relating to Technical Specification amendments issued for the Turkey Point Plant; therefore she has been added to the distribution list for all correspondence the staff sends to FPL in relation to the Turkey Point Plant; As such, she will receive a copy of the staff's approval or denial of the FPL exemption request, including the basis for the staff's determination.
I trust you find this responsive to your request and of assistance in assuring yourself and your constituents that there is no immediate safety concern in relation to the existing pressure-temperature limits of the Turkey Point reactor vessels as specified in the Technical Specifications.
The staff's approval or denial of the exemption request and any subsequent actions will be based on sound technical judgement and will be consistent with the Commission's policy of ensuring all operating facilities achieve and maintain adequate levels of protection of public health and safety.
If we can be of further assistance, please do not hesitate to contact us.
Sincerely,
Enclosures:
As stated
~ca) T. A, itdun Victor Stello, Jr.
Executive Director for Operations
- See previous concurrence
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The Honorable Dante B. Fa'scell i.
The purpose of"'the reactor vessel material surveillance program is to monitor the effects of neutron irradiation damage and the thermal environment on the reactor vessel beltline material integrity.
The analysis of the surveillance capsules serves to determine the safety margin of the beltline material associated with the pressure-temperature limits as required by Appendix G of 10 CFR Part 50.
The existing Technical Specifications for the Turkey Point Plant, Units 3 and 4, include pressure-temperature limits to be effective for the first 10 Effective Full Power Years (EFPY) of operation for both units.
As of May 31, 1986, exposure for the Unit 3 reactor vessel is 8.7 EFPY and the present exposure for Unit 4 is 8.31 EFPY.
These present exposures are below the allowable limit as set forth in the operating licenses, and the summary report of the capsule in question will be submitted well in advance of reaching the licensing limit.
- Hence, there is an adequate margin between the actual amount of neutron irradiation exposures to both reactor vessels and the exposure permitted by the operating
'licenses.
In summary, there is no immediate safety concern based on the reactor vessel neutron exposure of each unit, which is well below the allowable limits required by the Turkey Point Plant Technical Specifications.
The staff is currently evaluating FPL's exemption request pursuant to 10 CFR 50.12.
I would like to note that Ms. Lorian initiated proceedings relating to Technical Specification amendments issued for the Turkey Point Plant; therefore she has been added to the distribution list for all correspondence the staff sends to FPL in relation to the Turkey Point Plant.
As such, she will receive a copy of the staff's approval or denial of the FPL exemption request, including the basis for the staff's determination.
I trust you find this responsive to your request and of assistance in assuring yourself and your constituents that there is no immediate safety concern in relation to the existing pressure-temperature limits of the Turkey Point reactor vessels as specified in the Technical Specifications.
The staff's approval or denial of the exemption request and any subsequent actions will be based on sound technical judgement and will be consistent with the Commission's policy of ensuring all operating facilities achieve and maintain adequate levels of protection of public health and safety.
If we can be of further assistance, please do not hesitate to contact us.
Sincerely, Victor Stello, Jr.
Executive Director for Operations
Enclosures:
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