NRC Generic Letter 1981-25: Difference between revisions

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| issue date = 06/13/1981
| issue date = 06/13/1981
| title = NRC Generic Letter 1981-025: Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans
| title = NRC Generic Letter 1981-025: Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans
| author name = Eisenhut D G
| author name = Eisenhut D
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 4
| page count = 4
}}
}}
{{#Wiki_filter:Cf tLPA REG(,, F EUNITED STATES NUCLEAR REGULATORY  
{{#Wiki_filter:Cf tLPA REG(,,
COMMISSION
                    F     EUNITED                     STATES
WASHINGTON, D. C. 20555 TO ALL HOLDERS OF CONSTRUCTION  
                                    NUCLEAR REGULATORY COMMISSION
PERMITS Gentlemen:
                                            WASHINGTON, D. C. 20555 TO ALL HOLDERS OF CONSTRUCTION PERMITS
SUBJECT: CHANGE IN IMPLEMENTING  
              Gentlemen:
SCHEDULE FOR SUBMISSION  
              SUBJECT:     CHANGE IN IMPLEMENTING SCHEDULE FOR SUBMISSION AND EVALUATION
AND EVALUATION
                          OF UPGRADED EMERGENCY PLANS (Generic Letter No. 81-25)
OF UPGRADED EMERGENCY  
              On October 31, 1980, you were provided a clarification letter (NUREG-0737)
PLANS (Generic Letter No. 81-25)On October 31, 1980, you were provided a clarification letter (NUREG-0737)
              regarding approved TMI Action.Plan items. The implementation schedule           implies for item III.A.2 Emergency Preparedness in Enclosure 2, NUREG-0737,Revision            1, that upgraded emergency plans to meet the criteria         of NUREG-0654,
regarding approved TMI Action.Plan items. The implementation schedule for item III.A.2 Emergency Preparedness in Enclosure  
              "Criteria for Preparation and Evaluation of Radiological         Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" must be submitted prior to fuel load authorization. Full compliance with all elements of NUREG 0654 is unnecessary for this stage of startup operations.
2, NUREG-0737, implies that upgraded emergency plans to meet the criteria of NUREG-0654, Revision 1,"Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" must be submitted prior to fuel load authorization.


Full compliance with all elements of NUREG 0654 is unnecessary for this stage of startup operations.
Enclosed is a copy of page 2-11 of Enclosure 2, NUREG-0737, changing            the implementing schedule to require upgraded        emergency  plans  from  prior  to
              "fuel load" to prior to "full-power"    authorization.      The requirements necessary for a "fuel load" authorization will be determined on a case- by-case basis.


Enclosed is a copy of page 2-11 of Enclosure  
Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosure:
2, NUREG-0737, changing the implementing schedule to require upgraded emergency plans from prior to"fuel load" to prior to "full-power" authorization.
                Page 2-11 of Enclosure 2, NUREG-0737 PDR ADOC305000275 F                    D


The requirements necessary for a "fuel load" authorization will be determined on a case-by-case basis.Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosure:
s - I
Page 2-11 of Enclosure
                                                                                                                                                V Il ENCLOSURE 2 (COtITInUED)
2, NUREG-0737 PDR ADOC3 0500027 5 F D
Clarifi-                                                                 Implemen-       Plant   Require- Clarifi-   Tech Carion                                                                   tatlon         Applica- ments     cation     Spec.
s -I V Il ENCLOSURE  
 
2 (COtITInUED)
Iten           Title                   Description                     Schedule       b 1ity   Issued   Issued     Req.     Remarks
Clarifi- Implemen- Plant Require- Clarifi- Tech Carion tatlon Applica- ments cation Spec.Iten Title Description Schedule b 1ity Issued Issued Req. Remarks 1i.K.3 rFnal Recomfendations, c. New analyses In accordance All
  1i.K.3       rFnal Recomfendations,       c. New analyses             Inaccordance All       *         Encl. 3     No B6O task force                                           with review (Continued)                                             schedule
* Encl. 3 No B6O task force with review (Continued)  
                                        31. Plant-specific analysis     1/1/03f       All     *         Enc. 3       ho
schedule 31. Plant-specific analysis 1/1/03f All
                                        44. Evaluate transients         1/1/lIA         OUR     *         Encl. 3   As with single failure                                                       required
* Enc. 3 ho 44. Evaluate transients  
                                        45. Manual depressurization     1/81A         OWR     *         Encl. 3   No
1/1/lIA OUR
                                        46. Michelson concerns           fuel load     DMR     *         Encl. 3   no III.A.I.I
* Encl. 3 As with single failure required 45. Manual depressurization  
III.A.1.2 Emergency preparedness, short term Upgrade emergency Sho.t-term improvements
1/81A OWR
                                          1. Establish TSC OSC
* Encl. 3 No 46. Michelson concerns fuel load DMR
                                                                          Complete TOD             All All
* Encl. 3 no III.A.I.I  
                                                                                                  9/27I79
Emergency Sho.t-term improvements Complete no preparedness, short term III.A.1.2 Upgrade emergency  
                                                                                                  92/
1. Establish TSC OSC TOD All 9/27I79 11/9/79 No support facilities EOF (interim bas'sl TOD All 92/ 1/7 To 2. Design TOO T BO T OO T BO T hD 3. Modifications  
                                                                                                            11/9/79
100 TOo TOO TOD TOD 11I.A.2 Lsimrtqency  
                                                                                                              1/7 no No To I
1. Upgrade aaergency plans full power All 8/19/11 NIREG- Yes preparedness to App E. 10 CFR 50 (K54 2. Meteorological data Full power All 6/26/80 NUREG- Yes 0654 111.U.1.1 Primary coolant Measure leak rates I Full power All 9/27/79 11/9/79 Yes outside establish program to Encl. 3 containment keep leakage ALARA 111.0.3.3 Inplant 12 radiation  
                support facilities         EOF (interim bas'sl         TOD
1. Provide means to Fuel load All 9/27/79 11/9/79 Yes monitoring determine presence Encl. 3 of radio1odine
                                                                                        T BO     T OO     T BO       T hD
2. Modifications to 1/1/81 or All 9/27/79 11/9/79 Yes accurately measure prior to radlolodine icensing Encl. 3 111.0.3.4 Control-room  
                                                                                                                                        I
1. Identify and evaluate Full power All 6/26/80 End. 3 No habitability potential hazards 2. Schedule for Full power All 6/26/00 End. 3 o modifications
                                          2. Design                      TOO
3. Modifications full power All 6/26/80 Encl. 3 Yes AFoisr vitonts before operating license Is issued or 4 months before date indicated.
                                          3. Modifications               100             TOo     TOO       TOD       TOD
11I.A.2         Lsimrtqency             1.Upgrade aaergency plans       full power   All     8/19/11     NIREG-     Yes preparedness                 to App E. 10 CFR 50                                             (K54
                                          2. Meteorological data         Full power       All     6/26/80   NUREG-     Yes
                                                                                                            0654
111.U.1.1     Primary coolant           Measure leak rates I             Full power     All       9/27/79   11/9/79   Yes outside                 establish program to                                               Encl.3 containment             keep leakage ALARA
111.0.3.3     Inplant12 radiation       1.Provide means to           Fuel load         All     9/27/79   11/9/79   Yes monitoring                 determine presence                                             Encl.3 of radio1odine
                                          2.Modifications to           1/1/81 or         All     9/27/79   11/9/79   Yes accurately measure         prior to radlolodine                   icensing                       Encl.     3                   -
  111.0.3.4       Control-room             1. Identify and evaluate     Full power       All   6/26/80   End.3         No                 n habitability                 potential hazards
                                          2. Schedule for                 Full power     All   6/26/00   End.3       o                   t0
                                              modifications
                                          3.
 
Modifications                   full power     All     6/26/80 Encl.     3   Yes AFoisr vitonts before operating license Is issued or 4 months before date indicated.
 
*hequirement formally issued by this letter.


*hequirement formally issued by this letter.I I-n t0
PLANTS UNDER CONSTRUCTION
PLANTS UNDER CONSTRUCTION
1.2.3.4.5.Cherokee 1/2/3 Beaver Valley 2 St. Lucie 2 Vogtle 1/2 River Bend 1/2 50-491, 50-412 50-389 50-424, 50-458, 492, 493 425 459 6.7.8.9.10.11.12.13.Forked River Nine Mile Point 2 Millstone
    Cherokee 1/2/3               50-491, 492, 493
3 Bailly 2 Limerick 1/2 Hope Creek 1/2 Seabrook 1/2 50-363 50-410 50-423 50-367 50-352, 50-354, 50-443, 353 355 444 14.15.16.17.18.19.20.Hartsville  
1.
1/2/3/4 Phipps Bend 1/2 Yellow Creek 1/2 WPPSS 1/3/4/5 Harris 1/2/3/4 FNP 50-518, 50-553, 50-566, 50-460, 50-400, 50-437 519, 554 567 508, 401, 520, 521 513, 509 402, 403 PLANTS UNDER OL REVIEW 1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.19.20.21.22.23.24.25.26.27.28.29.Clinton 1/2 Byron 1/2 Braidwood
 
1/2 LaSalle 1/2 Midland 1/2 McGuire 2 So. Texas 1/2 Shoreham Waterford Grand Gulf 1/2 Diablo Canyon 1/2 Susquehana
Beaver Valley 2             50-412
1/2 St. Lucie 2 Summer 1 San Onofre 2/3 Bellefonte
2.
1/2 Watts'Bar
 
1/2 Sequoyah 2 Comanche Peak 1/2 50-461/462
3. St. Lucie 2                 50-389 Vogtle 1/2                   50-424, 425
50-454, 455 50-456/457
4.
50-373, 374 50-329,330
 
50- 370 50-498, 499 50-322 50-382 50-416/417
50-458, 459
50-275, 323 50-387, 388 50-389 50-395 50-361, 362 50-438, 439 50-390, 391 50- 328 50-445, 446 WPPSS-2 Fermi 2 Ziimmer 1 Perry 1/2 Palo Verde Catawba Marble Hill Wolf Creek Callaway 50-397 50-341 50-358 50-440, 50-528, 50-413, 50-546, 50-4 82 50-483, 441 529, 530 414 547 486}}
5. River Bend 1/2
6.
 
Forked River                50-363
7.
 
Nine Mile Point 2            50-410
8.
 
Millstone 3                  50-423
9.
 
Bailly 2                      50-367
10.
 
50-352, 353
11. Limerick 1/2 Hope Creek 1/2               50-354, 355
12.
 
Seabrook 1/2                 50-443, 444
13.
 
14.
 
50-518, 519, 520, 521
15. Hartsville 1/2/3/4 Phipps Bend 1/2             50-553, 554
16.
 
Yellow Creek 1/2             50-566, 567
17.
 
WPPSS 1/3/4/5               50-460, 508, 513, 509
18.
 
Harris 1/2/3/4               50-400, 401, 402, 403
19.
 
20.  FNP                          50-437
 
PLANTS UNDER OL REVIEW
1. Clinton 1/2                     50-461/462
2. Byron 1/2                       50-454, 455
3. Braidwood 1/2                   50-456/457
4. LaSalle 1/2                      50-373, 374
5. Midland 1/2                      50-329,330
6. McGuire    2                    50-     370
7. So. Texas 1/2                    50-498, 499
8. Shoreham                        50-322
9. Waterford                        50-382
10. Grand Gulf 1/2                  50-416/417
11. Diablo Canyon 1/2                50-275, 323
12. Susquehana 1/2                  50-387, 388
13. St. Lucie 2                      50-389
14. Summer 1                        50-395
15. San Onofre 2/3                  50-361, 362
16. Bellefonte 1/2                  50-438, 439
17. Watts'Bar 1/2                    50-390, 391
18. Sequoyah    2                  50-     328
19. Comanche Peak 1/2                50-445, 446
20.
 
21. WPPSS-2                         50-397
22. Fermi 2                          50-341
23. Ziimmer 1                        50-358
24. Perry 1/2                        50-440, 441
25. Palo Verde                      50-528, 529, 530
26. Catawba                          50-413, 414
27. Marble Hill                      50-546, 547
28. Wolf Creek                      50-4 82
29. Callaway                        50-483, 486}}


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Latest revision as of 03:06, 24 November 2019

NRC Generic Letter 1981-025: Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans
ML031080613
Person / Time
Site: Beaver Valley, Millstone, Mcguire, Nine Mile Point, Palo Verde, Perry, Fermi, Catawba, Harris, Wolf Creek, Saint Lucie, Watts Bar, Hope Creek, Grand Gulf, Sequoyah, Byron, Braidwood, Susquehanna, Summer, Columbia, Seabrook, Limerick, River Bend, Diablo Canyon, Callaway, Vogtle, Waterford, Clinton, South Texas, San Onofre, Comanche Peak, Midland, Bellefonte, LaSalle, 05000363, 05000000, Zimmer, Washington Public Power Supply System, Shoreham, Satsop, Bailly, Atlantic Nuclear Power Plant, Cherokee, Marble Hill, Hartsville, Phipps Bend, Yellow Creek
Issue date: 06/13/1981
From: Eisenhut D
Office of Nuclear Reactor Regulation
To:
References
GL-81-025, NUDOCS 8107100320
Download: ML031080613 (4)
v • d • e


Cf tLPA REG(,,

F EUNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555 TO ALL HOLDERS OF CONSTRUCTION PERMITS

Gentlemen:

SUBJECT: CHANGE IN IMPLEMENTING SCHEDULE FOR SUBMISSION AND EVALUATION

OF UPGRADED EMERGENCY PLANS (Generic Letter No. 81-25)

On October 31, 1980, you were provided a clarification letter (NUREG-0737)

regarding approved TMI Action.Plan items. The implementation schedule implies for item III.A.2 Emergency Preparedness in Enclosure 2, NUREG-0737,Revision 1, that upgraded emergency plans to meet the criteria of NUREG-0654,

"Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" must be submitted prior to fuel load authorization. Full compliance with all elements of NUREG 0654 is unnecessary for this stage of startup operations.

Enclosed is a copy of page 2-11 of Enclosure 2, NUREG-0737, changing the implementing schedule to require upgraded emergency plans from prior to

"fuel load" to prior to "full-power" authorization. The requirements necessary for a "fuel load" authorization will be determined on a case- by-case basis.

Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosure:

Page 2-11 of Enclosure 2, NUREG-0737 PDR ADOC305000275 F D

s - I

V Il ENCLOSURE 2 (COtITInUED)

Clarifi- Implemen- Plant Require- Clarifi- Tech Carion tatlon Applica- ments cation Spec.

Iten Title Description Schedule b 1ity Issued Issued Req. Remarks

1i.K.3 rFnal Recomfendations, c. New analyses Inaccordance All * Encl. 3 No B6O task force with review (Continued) schedule

31. Plant-specific analysis 1/1/03f All * Enc. 3 ho

44. Evaluate transients 1/1/lIA OUR * Encl. 3 As with single failure required

45. Manual depressurization 1/81A OWR * Encl. 3 No

46. Michelson concerns fuel load DMR * Encl. 3 no III.A.I.I

III.A.1.2 Emergency preparedness, short term Upgrade emergency Sho.t-term improvements

1. Establish TSC OSC

Complete TOD All All

9/27I79

92/

11/9/79

1/7 no No To I

support facilities EOF (interim bas'sl TOD

T BO T OO T BO T hD

I

2. Design TOO

3. Modifications 100 TOo TOO TOD TOD

11I.A.2 Lsimrtqency 1.Upgrade aaergency plans full power All 8/19/11 NIREG- Yes preparedness to App E. 10 CFR 50 (K54

2. Meteorological data Full power All 6/26/80 NUREG- Yes

0654

111.U.1.1 Primary coolant Measure leak rates I Full power All 9/27/79 11/9/79 Yes outside establish program to Encl.3 containment keep leakage ALARA

111.0.3.3 Inplant12 radiation 1.Provide means to Fuel load All 9/27/79 11/9/79 Yes monitoring determine presence Encl.3 of radio1odine

2.Modifications to 1/1/81 or All 9/27/79 11/9/79 Yes accurately measure prior to radlolodine icensing Encl. 3 -

111.0.3.4 Control-room 1. Identify and evaluate Full power All 6/26/80 End.3 No n habitability potential hazards

2. Schedule for Full power All 6/26/00 End.3 o t0

modifications

3.

Modifications full power All 6/26/80 Encl. 3 Yes AFoisr vitonts before operating license Is issued or 4 months before date indicated.

  • hequirement formally issued by this letter.

PLANTS UNDER CONSTRUCTION

Cherokee 1/2/3 50-491, 492, 493

1.

Beaver Valley 2 50-412

2.

3. St. Lucie 2 50-389 Vogtle 1/2 50-424, 425

4.

50-458, 459

5. River Bend 1/2

6.

Forked River 50-363

7.

Nine Mile Point 2 50-410

8.

Millstone 3 50-423

9.

Bailly 2 50-367

10.

50-352, 353

11. Limerick 1/2 Hope Creek 1/2 50-354, 355

12.

Seabrook 1/2 50-443, 444

13.

14.

50-518, 519, 520, 521

15. Hartsville 1/2/3/4 Phipps Bend 1/2 50-553, 554

16.

Yellow Creek 1/2 50-566, 567

17.

WPPSS 1/3/4/5 50-460, 508, 513, 509

18.

Harris 1/2/3/4 50-400, 401, 402, 403

19.

20. FNP 50-437

PLANTS UNDER OL REVIEW

1. Clinton 1/2 50-461/462

2. Byron 1/2 50-454, 455

3. Braidwood 1/2 50-456/457

4. LaSalle 1/2 50-373, 374

5. Midland 1/2 50-329,330

6. McGuire 2 50- 370

7. So. Texas 1/2 50-498, 499

8. Shoreham 50-322

9. Waterford 50-382

10. Grand Gulf 1/2 50-416/417

11. Diablo Canyon 1/2 50-275, 323

12. Susquehana 1/2 50-387, 388

13. St. Lucie 2 50-389

14. Summer 1 50-395

15. San Onofre 2/3 50-361, 362

16. Bellefonte 1/2 50-438, 439

17. Watts'Bar 1/2 50-390, 391

18. Sequoyah 2 50- 328

19. Comanche Peak 1/2 50-445, 446

20.

21. WPPSS-2 50-397

22. Fermi 2 50-341

23. Ziimmer 1 50-358

24. Perry 1/2 50-440, 441

25. Palo Verde 50-528, 529, 530

26. Catawba 50-413, 414

27. Marble Hill 50-546, 547

28. Wolf Creek 50-4 82

29. Callaway 50-483, 486

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