ML17199S954
| ML17199S954 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/16/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17199S953 | List: |
| References | |
| NUDOCS 8709210065 | |
| Download: ML17199S954 (4) | |
Text
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DRESDEN NUCLEAR POWER STATION UNIT NOS. 2 AND 3 INTERIM SAFETY EVALUATION ENCLOSURE
- 1.
The licensee's proposed measurement of pump vibration in terms of veloci.ty is an acceptable method.
However, the licensee's proposed limits are not acceptable.
The limits proposed do not ensure that pump vibration will remain at an acceptable value.
Th~s, while the staff.*
approves the use of velocity as a parameter to be measured to indicate pump vibration, the staff disapproves the proposed limits. The limits may be based on the ASME OM-6 vibration limits which have been utilized by other facilities and found acceptable to the staff.
- 2.
The licensee has requested relief from exercising valves 2-305-115, 3-305-115, accumulator charging water header checks, 2-305-138, and 3-305-138, control rod drive cooling water header checks, in accordance with requirements of Section XI and proposed to full-stroke exercise these valves during refueling outages.
The staff does not agree with the licensee's basis because the licensee ha*s not described the method utilized to individually verify valve closure, therefore, relief is not granted from the exercising requirements of Section XI for valves -115 and -138.
The -115 and -138 valves cannot be verified to shut during individual control rod scram testing because the hydraulic control unit accumulator charging line and the control rod drive mechanism cooling water i;ne are pressurized whenever a control rod drive pump is running and the differential pressure developed across either check valve may not be sufficient to close it. However, the control rod drive pump cannot be
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stopped during power operation because that could result in damage to the control rod drive mechanism seals and the recirculation pump seals due to overheating. Also, the control rod drive pump cannot be secured during cold shutdowns because one recirculation pump is usually run to ensure proper mixing in the core and the running pump must be supplied with seal water.
On this basis, the staff agrees with the licensee's proposed refueling outage test frequency.
However, the licensee will be required to develop refueling outage test methods to verify the position of these valves. These test methods must be submitted for NRC review for final approval of the relief request.
- 3.
The licensee will* be required to develop a test method to verify the position of CRD valves 2-305-115, 3-305-115,' accumulator charging water header checks, 2-305-138, and 3-305-138, control rod drive cooling water header checks, during refueling outages.
- 4.
The licensee will be required to disassemble valves 2-2301-39 and 3-2301-39, high pressure coolant injection torus suction checks, at a refuel.ing outage frequency until inspection results allow lengthening the inspection interval.
- 5.
The licensee will be required to change the definition of fast-acting valves from "those that stroke in 5 seconds or less" to "those that stroke in 2 seconds or less".
- 6.
The following items were discussed via telephone with the licensee.
These changes are to correct typographical and/or clerical errors only and do not alter the contents of any request for relief or evaluation of that request in the licensee's report.
- a.
Page 21 of 40, Unit 2:
The category of valves 2-1501-13A and 2-1501-138 should be Category 8 instead of blank.
- b.
Page 29 of 40, Unit 2:
The normal position of valve 2-2301-29 should be 110 11 instead of 11C 11 *
- c.
Page 30 of 40, Unit 2:
The stroke direction of valve 2-2301-51.
should be "C" instead of 110 11 *
- d.
Page 29 of 40, Unit 3:
The stroke direction of valve 3-2301-20 should be 110 11 instead of 110/C 11 *
- e.
Relief Re_quest No. VR-4:
Valves 2-1101-15, 2-1101-16, 3-1101-15, and 3-1101-16 should be Category A/C instead of Category C.
- f.
Relief Request No. VR-5:
V~lves 2-205-2-7 and 3-205-2-7 should be Category A/C instead of Category C.
- g.
Relief Request No. VR-8:
Valves 2-1402-9A, 2-1402-98, 3-1402-9A, 3-1402-98, 2-1501-25A, 2-1501-258, 3-1501-25A, and 3-1501-258 should be Category A/C instead of Category C.
- h.
Relief Request No. VR-10:
Valves 2-2301-34, 3-2301-34, 2-2301-45, and 3-2301-45 should be Category A/C instead of Category C.
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- i.
Relief Request No. VR-13:
Valves 2-220-58A, 2-220-588, 3-220-58A, 3:220-588, 2-220-62A, 2-220-628, 3-220-62A, and 3-220-628 should be Category A/C instead of Category C.
- j.
Relief Request No *. VR-14:
Valves 3-1601-31A and 3-1601-318 should be Category A/C instead of Category C.
- k.
Relief Request No. VR-15:
Valves 2-743 and 3-743 should be Category A/C instead of Category C.
- l.
Relief Request No. VR-12:
This relief request should reference IWV-3512 and PTC-25.3-1976 instead of IWV-3510(b) and PTC-25.2-1966.
- m.
Relief Request No. VR-16:
This relief request should reference IWV-3413(c) instead of IWV-3410(c)(3).
- n.
The title page of Section 4.2 should identify Units 2 and 3 instead of Units 1 and 2.
- o.
Section 3.1 should identify pumps whose inlet pressure is calculated as agreed upon during the September 1982 conference calls.
- p.
Relief Request No. PR-1:
This relief request should identify the vibration velocity ranges in the table "Allowable Ranges of Test Quantities".
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